Changes in risk perceptions before and after nuclear accidents; Evidence from Japan

Nishikawa, Masashi*; Kato, Takaaki*; Homma, Toshimitsu; Takahara, Shogo

Environmental Science & Policy, 55(Part 1), p.11 - 19, 2016/01

https://doi.org/10.1016/j.envsci.2015.08.015

Effects of -radiation on a direct disposal system for spent nuclear fuel, 2; Review of research into safety assessments of direct disposal of spent nuclear fuel in Europe and North America

Kitamura, Akira; Takase, Hiroyasu*; Metcalfe, R.*; Penfold, J.*

Journal of Nuclear Science and Technology, 53(1), p.19 - 33, 2016/01

https://doi.org/10.1080/00223131.2015.1014874

Not only geological disposal of vitrified waste generated by spent fuel (SF) reprocessing, but also the possibility of disposing of SF itself in deep geological strata (hereinafter "direct disposal of SF") may be considered in the Japanese geological disposal program. In the case of direct disposal of SF, the radioactivity of the waste is higher and the potential effects of the radiation are greater. Specific examples of the possible effects of radiation include: increased amounts of canister corrosion; generation of oxidizing chemical species in conjunction with radiation degradation of groundwater and accompanying oxidation of reducing groundwater; and increase in the dissolution rate and the solubility of SF. Therefore, the influences of radiation, which are not expected to be significant in the case of geological disposal of vitrified waste, must be considered in safety assessments for direct disposal of SF. Focusing especially on the effects of -radiation in safety assessment, this study has reviewed safety assessments in countries other than Japan that are planning direct disposal of SF. The review has identified issues relevant to safety assessment for the direct disposal of SF in Japan.

Teleseismic shear wave tomography of the Japan subduction zone

Asamori, Koichi; Zhao, D.*

Geophysical Journal International, 203(3), p.1752 - 1772, 2015/12

https://doi.org/10.1093/gji/ggv334

We present the first high-resolution S-wave tomography of the Japan subduction zone down to a depth of 700 km, which is determined by inverting a large number of high-quality S-wave arrival-time data from local, regional and teleseismic events. The subducting Pacific and Philippine Sea (PHS) slabs are revealed clearly as high-velocity (high-V) zones, whereas low-velocity (low-V) anomalies are revealed in the mantle wedge above the two slabs. The PHS slab has subducted aseismically down to a depth of 480 km under the Japan Sea and to a depth of 540 km under the Tsushima Strait. A window is revealed within the aseismic PHS slab, being consistent with P-wave tomography. Prominent low-V anomalies exist below the PHS slab and above the Pacific slab, which reflect hot and wet mantle upwelling caused by the joint effect of deep dehydration of the Pacific slab and convective circulation process in the mantle wedge above the Pacific slab. The hot and wet mantle upwelling has caused the complex geometry and structure of the PHS slab in SW Japan, and contributed to the Quaternary volcanism along the Japan Sea coast. In eastern Japan, low-V zones are revealed at depths of 200-700 km below the Pacific slab, which may reflect hot upwelling from the lower mantle or even the core-mantle boundary.

Supposed existence of Np in a genuine dissolver solution from the results of extraction simulation by PARC-L code

Asakura, Toshihide; Hotoku, Shinobu; Morita, Yasuji

Journal of Nuclear Science and Technology, 52(12), p.1552 - 1561, 2015/12

https://doi.org/10.1080/00223131.2015.1018361

With a genuine spent fuel soltuion (a dissolver solution), a laboratory-scale reprocessing experiment of an extraction-separation process was performed using mixer-settlers as extactors. In the experiment, n-butyraldehyde was utilized as a reducing reagent of NpO to NpO for the purpose to distinguish NpO from Np. From the Np concentration in the aqueous phase, Np would be extracted from the dissolver solution together with U and Pu. The scrutiny of Np behavior was performed utilizing 66 cases of calculation results by a Japan Atomic Energy Agency open extraction simulation code, the Programm for Advanced Extraction with Radiation Effect Calculation-Lightened version. From the scrutiny, the authors found that the calculation result with 60% of Np in the dissolver solution represented the best experimental extraction-separtion behavior of Np. Therefore, it was supposed that the dissolver solution contained sufficient proportion of Np to affect the extraction-separation behavior of Np.

Thermohydraulic responses of a water-cooled tokamak fusion DEMO to loss-of-coolant accidents

Nakamura, Makoto; Tobita, Kenji; Someya, Yoji; Uto, Hiroyasu; Sakamoto, Yoshiteru; Gulden, W.*

Nuclear Fusion, 55(12), p.123008_1 - 123008_7, 2015/12

https://doi.org/10.1088/0029-5515/55/12/123008

Major in- and ex-vessel loss-of-coolant accidents (LOCAs) of a water-cooled tokamak fusion DEMO reactor have been analysed. Analyses have identified responses of the DEMO systems to these accidents and pressure loads to confinement barriers for radioactive materials. The thermohydraulic analysis results suggests that the in- and ex-vessel LOCAs crucially threaten integrity of the primary and final confinement barriers, respectively. As for the in-vessel LOCA, it was found that the pressure in the vacuum vessel reaches its design value due to the LOCA even though a pressure suppression system is in service. As for the ex-vessel LOCA, the pressure load to the tokamak hall due to the double-ended break of the primary cooling pipe was found to be so large that integrity of the hall was crucially challenged. Mitigations of the loads to the confinement barriers are also discussed.

A Numerical study on local fuel-coolant interactions in a simulated molten fuel pool using the SIMMER-III code

Cheng, S.; Matsuba, Kenichi; Isozaki, Mikio; Kamiyama, Kenji; Suzuki, Toru; Tobita, Yoshiharu

Annals of Nuclear Energy, 85, p.740 - 752, 2015/11

https://doi.org/10.1016/j.anucene.2015.06.030

Concentration and characterization of organic colloids in deep granitic groundwater using nanofiltration membranes for evaluating radionuclide transport

Aosai, Daisuke*; Saeki, Daisuke*; Iwatsuki, Teruki; Matsuyama, Hideto*

Colloids and Surfaces A; Physicochemical and Engineering Aspects, 485, p.55 - 62, 2015/11

AA2015-0227.pdf:1.14MB

https://doi.org/10.1016/j.colsurfa.2015.09.012

To analyze organic colloids in deep groundwater, concentration techniques using adsorption resins and reverse osmosis membranes have been widely applied, because their concentrations in deep groundwater are very low and detection of the organic colloids in raw groundwater is difficult. However, these techniques have respective disadvantages such as chemical disturbance and membrane fouling caused by cations. To overcome their disadvantages, we propose a new concentration method using nanofiltration membranes to concentrate organic colloids rapidly without chemical disturbance and to selectively remove monovalent and divalent ions, which may cause inorganic and/or organic fouling. Concentration performance of the NF and RO membranes for aqueous solutions for humic acids was evaluated using a laboratory-scale membrane test unit. The time course of permeate flux and concentration of humic acids were measured. These membranes were applied to the concentration of actual groundwater.

Development of operation scenarios for plasma breakdown and current ramp-up phases in JT-60SA tokamak

Urano, Hajime; Fujita, Takaaki*; Ide, Shunsuke; Miyata, Yoshiaki; Matsunaga, Go; Matsukawa, Makoto

Fusion Engineering and Design, 100, p.345 - 356, 2015/11

https://doi.org/10.1016/j.fusengdes.2015.06.138

The operation scenarios for plasma breakdown and current ramp-up phases in JT-60SA tokamak have been developed. The induced current in the in-vessel conducting elements such as vacuum vessel and stabilizing plate increases to the comparable level of plasma current of 600 kA during the breakdown phase and thus enhances the strength of error field. The optimized scenarios for half and full pre-magnetization cases satisfied the conditions required for the plasma initiation. At the initial plasma, the vertical magnetic field required to sustain the plasma position was controlled by the outer equilibrium field (EF) coil currents which compensate for a vertical field due to a large eddy current. The condition for the formation of divertor configurations given by the combination of the magnetic flux for plasma and the plasma current enables us to develop the operational scenarios with a smooth transition from a limiter to a divertor configuration.

Issues associated with radiation protection after Fukushima Daiichi Nuclear Power Plant disaster

Yamasoto, Kotaro

Gijutsushi, 27(11), p.8 - 11, 2015/11

Various analysis reports focused on Fukushima Daiichi Nuclear Power Plant disaster have been published from government, national diet, private group and Tokyo electric power company. Japan Health Physics Society (JHPS) analyzed these reports on perspective of radiation protection, and has reported towards the national and international society as "second-order recommendation report". What are radiation protection issues that have been found from these analysis reports? What is the direction of the goal of radiation protection system at the time of nuclear accident? From the results of these analyzes, many challenges have been found in current nuclear disaster prevention system.

Introduction to neutron radiography

Iikura, Hiroshi; Sakai, Takuro; Matsubayashi, Masahito

Hamon, 25(4), p.277 - 282, 2015/11

https://doi.org/10.5611/hamon.25.4_277

We introduce the basic principle of neutron radiography technique, and the brief review of its applications. Most of works in this article have been performed at TNRF, Tokai, Japan. Neutron radiography is a nondestructive testing method, so that this technique is used for not only academic studies but also industrial applications. Keywords: neutron radiography, imaging, TNRF

Consideration of decontamination model for severe accident consequence assessment

Silva, K.*; Okamoto, Koji*; Ishiwatari, Yuki*; Takahara, Shogo; Promping, J.*

Journal of Nuclear Science and Technology, 52(11), p.1402 - 1416, 2015/11

https://doi.org/10.1080/00223131.2015.1005033

X-ray absorption spectroscopy in the heavy Fermion compound -YbAlB at high magnetic fields

Terashima, Taku*; Matsuda, Yasuhiro*; Kuga, Kentaro*; Suzuki, Shintaro*; Matsumoto, Yosuke*; Nakatsuji, Satoru*; Kondo, Akihiro*; Kindo, Koichi*; Kawamura, Naomi*; Mizumaki, Masaichiro*; et al.

Journal of the Physical Society of Japan, 84(11), p.114715_1 - 114715_4, 2015/11

https://doi.org/10.7566/JPSJ.84.114715

Study on erbium loading method to improve reactivity coefficients for low radiotoxic spent fuel HTGR

Fukaya, Yuji; Goto, Minoru; Nishihara, Tetsuo

Nuclear Engineering and Design, 293, p.30 - 37, 2015/11

AA2015-0102.pdf:0.79MB

https://doi.org/10.1016/j.nucengdes.2015.07.047

The investigation on the erbium loading method to improve reactivity coefficients for Low Radiotoxic Spent Fuel High Temperature Gas-cooled Reactor (LRSF-HTGR) is performed. The fuel employs HEU to reduce toxicity generation from uranium-238. The reactivity coefficients show positive values without any additive. Then, the erbium is loaded in the core to obtain negative reactivity coefficient due to the large resonance peak of neutron capture reaction of erbium-167. The loading methods are investigated. The erbium is mixed into fuel kernel of CPF, loaded by binary packing with fuel particle and erbium particle, and embedded into the graphite shaft deployed center of fuel compact. It is found that the erbium loading causes negative reactivity as a moderator temperature reactivity, and it should be loaded into fuel pin elements for pin-in-block type fuel from the viewpoint of heat transfer. Moreover, the erbium should be incinerated slowly to obtain negative reactivity coefficient even at EOC. The loading method which effectively causes self-shielding should be selected to avoid to be incinerated with burn-up. The mechanism is elucidated by application of Bondarenko approach. As a result, it is conclude that the erbium embedded into graphite shaft is preferable for LRSF-HTGR to remain the reactivity coefficient negative at EOC.

Improved strong scaling of a spectral/finite difference gyrokinetic code for multi-scale plasma turbulence

Maeyama, Shinya; Watanabe, Tomohiko*; Idomura, Yasuhiro; Nakata, Motoki; Nunami, Masanori*; Ishizawa, Akihiro*

Parallel Computing, 49, p.1 - 12, 2015/11

https://doi.org/10.1016/j.parco.2015.06.001

Inverse coherence effects in nuclear magnetic relaxation rates as a sign of topological superconductivity

Nagai, Yuki; Ota, Yukihiro; Machida, Masahiko

Physical Review B, 92(18), p.180502_1 - 180502_5, 2015/11

https://doi.org/10.1103/PhysRevB.92.180502

no abstracts in English

Mechanisms determining the structure of gold-catalyzed GaAs nanowires studied by in situ X-ray diffraction

Takahashi, Masamitsu; Kozu, Miwa*; Sasaki, Takuo; Hu, W.*

Crystal Growth & Design, 15(10), p.4979 - 4985, 2015/10

https://doi.org/10.1021/acs.cgd.5b00915

Seismic response analysis of reactor building and equipment using a 3D-FE model for reliability enhancement of seismic risk assessment of NPP

Nishida, Akemi; Igarashi, Sayaka*; Sakamoto, Shigehiro*; Muramatsu, Ken; Takada, Tsuyoshi*

Dai-8-Kai Kozobutsu No Anzensei, Shinraisei Ni Kansuru Kokunai Shimpojiumu (JCOSSAR 2015) Koen Rombunshu (CD-ROM), p.108 - 113, 2015/10

Research and development on next-generation seismic probabilistic risk assessment by using 3D vibration simulators is ongoing to evaluate the seismic safety performance of nuclear plants with high reliability. Most structural PRA uses probabilistic schemes such as the scheme that uses probabilistic seismic hazard and fragility curves. Even when earthquake ground motions are required in Monte Carlo Simulations (MCS), they are generated to fit the specified response spectra, such as uniform hazard spectra at a specified exceedance probability. However, these ground motions are not directly linked with their corresponding seismic source characteristics. In this context, the authors propose a methodology based on MCS to reproduce a set of input ground motions to develop an advanced PRA scheme. This paper describes the methodology to reproduce a set of input ground motions briefly and the analytical results of a nuclear plant building and equipment using the set of input ground motions.

Development of support system for large-scale underground structures using web 3D technology and RDBMS

Xu, Z.*; Yamachi, Hiroshi*; Sato, Toshinori; Matsui, Hiroya; Itakura, Kenichi*

Doboku Gakkai Rombunshu, F3 (Doboku Johogaku) (Internet), 71(1), p.43 - 55, 2015/10

In the process of underground space development, enormous information is collected in each developing stage, such as investigation, plan, design and construction. It is important to properly feed back these information to design and construction in order to realize rational design and construction of an underground space. And more, these information also become basic data in a plane of structure management. However, it is almost impossible that it is controlled in the individual ability, since collected information quantity is too enormous. For the purpose of intuitively controlling and processing these enormous information, we devised the system for the data management by freely moving in virtual reality space. In this paper, the basic structure of the system constructed by adopting WEB3D and RDBMS, is described, and the practicability is verified.

Development of a high power wideband polarizer for electron cyclotron current drive system in JT-60SA

Saigusa, Mikio*; Oyama, Gaku*; Matsubara, Fumiaki*; Takii, Keita*; Sai, Takuma*; Kobayashi, Takayuki; Moriyama, Shinichi

Fusion Engineering and Design, 96-97, p.577 - 582, 2015/10

https://doi.org/10.1016/j.fusengdes.2015.04.013

A wideband polarizer has been developed for an ECCD system in JT-60SA. The groove depth of the mirrors installed in miter bends were optimized for two frequencies (110 GHz and 138 GHz) by numerical simulations. All surfaces of Poincare spheres were covered at both of the frequencies in low power test. The thermal stress of polarizer were estimated by the numerical simulations. The twister polarizer has been tested up to 0.24 MW during 3 s at 110 GHz.

Upgrade in catalytic activity of hydrophobic platinum catalysts by irradiation with electron beams

Iwai, Yasunori

Fusion Engineering and Design, 98-99, p.1796 - 1799, 2015/10

https://doi.org/10.1016/j.fusengdes.2015.03.024

Hydrophobic platinum catalysts have been widely applied in the field of nuclear fusion for the exchange reactions of hydrogen isotopes between hydrogen and vapor in the water detritiation system, and for the oxidation of tritium on the atmospheric detritiation system. Hydrophobic platinum catalysts are hardly susceptible to water mist and water vapor. Hydrophobic platinum catalysts are produced by supporting platinum directly on hydrophobic polymer beads. For the hydrophobic polymer, styrene - divinyl benzene (SDB) has been applied in Japan. It can be pointed out that the upgrade in catalytic activity of hydrophobic catalyst is expected to downsize the catalytic reactor based on a hard look at a large increase in flow rate in future. The upgrade in catalytic activity of two types of commercial Pt/SDB catalysts was found when they were irradiated with electron beams. After irradiation with electron beams, the catalytic activity was evaluated by means of overall reaction rate constant for the oxidation of tritium. The overall reaction rate constant increased as increase in dose. The constant showed the peak value in the dose between 500 to 1000 kGy. After the peak, the constant decreased as increase in dose. The overall reaction rate constant at the peak was 6 times larger than that evaluated with unirradiated. The mechanical strength of irradiated Pt/SDB kept sound until 1500 kGy. The irradiation is a promising method to the upgrading in catalytic activity of Pt/SDB catalyst.

Development of instrumentation and control systems for the ITER diagnostic systems in JADA

Yamamoto, Tsuyoshi; Hashimoto, Yasunori*; Kitazawa, Sin-iti; Yatsuka, Eiichi; Hatae, Takaki; Sugie, Tatsuo; Ogawa, Hiroaki; Takeuchi, Masaki; Kawano, Yasunori; Itami, Kiyoshi

Fusion Engineering and Design, 96-97, p.1012 - 1016, 2015/10

https://doi.org/10.1016/j.fusengdes.2015.06.119

Japan Domestic Agency (JADA) is responsible for six diagnostic systems in the ITER project. We have successfully developed an instrumentation and control (I&C) system for the diagnostic systems. The I&C system manages internal operations for measurement such as health checks of sensors, configuration of measurement parameters, and consistency checks between measurement parameters. We developed a conversion tool to convert operational flowcharts to EPICS records. The sequencing management function coordinates the execution of operation steps by monitoring changes in the record values. It was designed so that the relationship between the records and steps is determined automatically according to the flowcharts as much as possible. We validated the performance of the I&C system for the thermocouple measurement system, and are continuing the development of even more complex I&C systems for other JADA diagnostic systems.

In-vessel coils for magnetic error field correction in JT-60SA

Matsunaga, Go; Takechi, Manabu; Sakurai, Shinji; Suzuki, Yasuhiro*; Ide, Shunsuke; Urano, Hajime

Fusion Engineering and Design, 98-99, p.1113 - 1117, 2015/10

https://doi.org/10.1016/j.fusengdes.2015.06.024

Estimation of the lifetime of resin insulators against baking temperature for JT-60SA in-vessel coils

Sukegawa, Atsuhiko; Murakami, Haruyuki; Matsunaga, Go; Sakurai, Shinji; Takechi, Manabu; Yoshida, Kiyoshi; Ikeda, Yoshitaka

Fusion Engineering and Design, 98-99, p.2076 - 2079, 2015/10

https://doi.org/10.1016/j.fusengdes.2015.06.018

The JT-60SA project is a EU - JA satellite tokamak under Broader Approach in support of the ITER project. In-vessel coils are designed and assembled by JA. The resin-insulator is required to have a heat resistance against the baking temperature of vacuum vessel of 200C (40000 hour). Thus the assessment of the heat load is fundamental for the design of the coils. However, the estimation of the lifetime of resin-insulator under the high-temperature region has not been examined. In the present study, the estimation of the lifetime of seven candidate resin-insulators such as epoxy resin and cyanate-ester resin under the 220C temperature region have been performed for the current coils design. Weight reduction of the seven candidate insulators was measured at different heating times under 180C, 200C and 220C environment using three thermostatic ovens, respectively. The reduction of the insulators has been used as input for Weibull-analysis towards Arrhenius-plot. Lifetime of the resins has been estimated for the first time at the high temperature region by the plot. Lifetime of the resin-insulators have been evaluated and discussed as well as the available temperature of the in-vessel coils.

Hydrophobic platinum honeycomb catalyst to be used for tritium oxidation reactors

Iwai, Yasunori; Kubo, Hitoshi*; Oshima, Yusuke*; Noguchi, Hiroshi*; Edao, Yuki; Taniuchi, Junichi*

Fusion Science and Technology, 68(3), p.596 - 600, 2015/10

https://doi.org/10.13182/FST14-921

We have newly developed the hydrophobic platinum honeycomb catalysts applicable to tritium oxidation reactor since the honeycomb-shape catalyst can decrease the pressure drop. Two types of hydrophobic honeycomb catalyst have been test-manufactured. One is the hydrophobic platinum catalyst on a metal honeycomb. The other is the hydrophobic platinum catalyst on a ceramic honeycomb made of silicon carbide. The fine platinum particles around a few nanometers significantly improve the catalytic activity for the oxidation tritium at a tracer concentration. The hydrogen concentration in the gaseous feed slightly affects the overall reaction rate constant for hydrogen oxidation. Due to the competitive adsorption of hydrogen and water molecules on platinum surface, the overall reaction rate constant has the bottom value. The hydrogen concentration for the bottom value is 100 ppm under the dry feed gas. We have experimentally confirmed the activity of these honeycomb catalysts is as good as that of pellet-shape hydrophobic catalyst. The results support the hydrophobic honeycomb catalysts are applicable to tritium oxidation reactor.

Research and development on nuclear transmutation by Accelerator Driven System (ADS)

Oigawa, Hiroyuki

Genshiryoku Nenkan 2016, p.133 - 135, 2015/10

An Accelerator-Driven System (ADS) is a hybrid nuclear system coupling a subcritical reactor with a spallation neutron source driven by a high-power proton accelerator, aiming at effective transmutation of minor actinides contained in high-level radioactive wastes. JAEA is conducting a research and development program on ADS, and planning to construct the Transmutation Experimental Facility at J-PARC as a part of the program.

Estimation of radioactive substance penetration in basement concrete

Tezuka, Masashi; Koda, Yuya; Fujita, Yoshihiko*; Kume, Kyo*

Heisei-26-Nendo Koeki Zaidan Hojin Wakasawan Enerugi Kenkyu Senta kenkyu Nempo, 17, P. 78, 2015/10

In order to contribute to the segregated management in accordance with the level of contamination such as dismantling products, as a basis frame concrete specimens of the condenser, which has been laid in the turbine building of the "Fugen", pre-observation of such cracks status of surface on which was carried out to investigate the pollution status of internal specimen.

Using LiF crystals for high-performance neutron imaging with micron-scale resolution

Faenov, A.*; Matsubayashi, Masahito; Pikuz, T.*; Fukuda, Yuji; Kando, Masaki; Yasuda, Ryo; Iikura, Hiroshi; Nojima, Takehiro; Sakai, Takuro; Shiozawa, Masahiro*; et al.

High Power Laser Science and Engineering, 3, p.e27_1 - e27_9, 2015/10

https://doi.org/10.1017/hpl.2015.28

Nuclear facilities and human resource development

Minato, Kazuo

Hokeikyo Nyusu, (56), P. 1, 2015/10

http://www.irm.or.jp/news56.pdf

The number of students who study nuclear engineering decreased after the accident at the Fukushima Dai-ichi Nuclear Power Station. Securing human resources and their development should be strongly promoted in cooperation with universities, industry, and research institutes since the universities hardly maintain and operate their nuclear facilities.

Radiation processing in my research life

Tamada, Masao

Hoshasen Kagaku (Internet), (100), P. 16, 2015/10

Collection of a rare metal form hot spring water attracted medias and had a public response by reports of numerous newspapers and television programs in my 35 years' research and development of radiation processing technologies and its technology management. Collection experiments of the rare metal were carried out in Kusatsu Onsen, Gunma prefecture, where discharge of hot spring water is the largest in Japan. We were on standby 6 am there when morning live broadcast started from 8 am. The invention of emersion grafting solved the problems in the cost reduction of adsorbent production owing to its high grafting yield and led the way for technology transfer of filter for the removal of metal ions in ppb level from semiconductor cleaning liquid and adsorbent for radio-active cesium.

Local structure analysis of KNbO nanocubes by solvothermal synthesis

Yoneda, Yasuhiro; Kohara, Shinji*; Nakashima, Koichi*; Nagata, Hajime*; Wada, Satoshi*

Japanese Journal of Applied Physics, 54(10S), p.10NC01_1 - 10NC01_6, 2015/10

https://doi.org/10.7567/JJAP.54.10NC01

The atomic-scale structure of KNbO nanopowder synthesized by solvothermal method has been studied using high-energy X-ray diffraction, Rietveld refinement, and the atomic pair-distribution function (PDF) technique. It was found that the local structure of KNbO nanoparticles deviates from the average structure. The local structure was found to be rhombohedral structure though the average structure was tetragonal structure. The rhombohedral distortion of NbO octahedra was maintained in the annealed sample.

Simulation of He embrittlement at grain boundaries of bcc transition metals

Suzudo, Tomoaki; Yamaguchi, Masatake

Journal of Nuclear Materials, 465, p.695 - 701, 2015/10

https://doi.org/10.1016/j.jnucmat.2015.07.002

To investigate what atomic properties largely determine vulnerability to He embrittlement at grain boundaries (GB) of bcc transition metals, we introduced a computational model composed of first principles density functional theory and a He segregation rate theory model. Predictive calculations of He embrittlement at the first wall of the future DEMO fusion concept reactor indicated that variation in the He embrittlement is originated not only from He production rate related to neutron irradiation, but also from the He segregation energy at the GB that has a systematic trend in the periodic table.

The Influences of Pu and Zr on the melting temperatures of the UO-PuO-ZrO pseudo-ternary system

Morimoto, Kyoichi; Hirooka, Shun; Akashi, Masatoshi; Watanabe, Masashi; Sugata, Hiromasa*

Journal of Nuclear Science and Technology, 52(10), p.1247 - 1252, 2015/10

https://doi.org/10.1080/00223131.2015.1047807

As a part of decommissioning plan of the damaged reactors at Fukushima Daiichi Nuclear Power Plant, some strategies for removing of debris from the reactors are discussed. In these considerations, it is necessary to predict a melt progression during the severe accident based on theoretical evidences. Melting temperature is one of the most important thermal characteristics to analyse a melt progression during the severe accident. In this study, the melting temperatures of specimens of U, Pu and Zr mixed oxide prepared as simulated debris were measured by the thermal arrest technique. From the results of this measurement, the influences of Pu and Zr contents on the melting temperature of the simulated debris were evaluated.

Thermophysical properties of americium-containing barium plutonate

Tanaka, Kosuke; Sato, Isamu; Hirosawa, Takashi; Kurosaki, Ken*; Muta, Hiroaki*; Yamanaka, Shinsuke*

Journal of Nuclear Science and Technology, 52(10), p.1285 - 1289, 2015/10

https://doi.org/10.1080/00223131.2015.1029554

Polycrystalline specimens of americium-containing barium plutonate have been prepared by mixing the appropriate amounts of (PuAm)O and BaCO powders followed by reacting and sintering at 1600 K under the flowing gas atmosphere of dry-air. The sintered specimens had a single phase of orthorhombic perovskite structure and were crack-free. The elastic moduli were determined from the longitudinal and shear sound velocities. The Debye temperature was also determined from the sound velocities and lattice parameter measurements. The thermal conductivity was calculated from the measured density at room temperature, literature values of heat capacity, and thermal diffusivity measured by laser flash method in vacuum. The thermal conductivity of americium-containing barium plutonate was roughly independent of the temperature and was almost the same magnitude as that of BaPuO and BaUO.

Fundamental experiments on phase stabilities of Fe-B-C ternary systems

Sudo, Ayako; Nishi, Tsuyoshi; Shirasu, Noriko; Takano, Masahide; Kurata, Masaki

Journal of Nuclear Science and Technology, 52(10), p.1308 - 1312, 2015/10

https://doi.org/10.1080/00223131.2015.1016465

For understanding the control blade degradation mechanism of BWR, the thermodynamic database for the fuel assembly materials is a useful tool. Although iron, boron, and carbon ternary system is a dominant phase diagram, phase relation data is not sufficient for the region in which the boron and carbon compositions are richer than the eutectic composition. The phase relations of three samples were analyzed by X-ray diffraction, scanning electron microscope and energy dispersed X-ray spectrometry. The results indicate that Fe(B,C) phase only exists in the intermediate region at 1273 K and that the solidus temperature widely maintains at about 1400 K for all three samples, which are different from the calculated data using previous thermodynamic database. The difference might be originated from the over-estimations of the interaction parameter between boron and carbon in Fe(B,C).

Study on minimum wall thickness requirement for seismic buckling of reactor vessel based on system based code concept

Takaya, Shigeru; Watanabe, Daigo*; Yokoi, Shinobu*; Kamishima, Yoshio*; Kurisaka, Kenichi; Asayama, Tai

Journal of Pressure Vessel Technology, 137(5), p.051802_1 - 051802_7, 2015/10

https://doi.org/10.1115/1.4029322

The minimum wall thickness required to prevent seismic buckling of a reactor vessel in a fast reactor is derived using the System Based Code (SBC) concept. One of the key features of SBC concept is margin optimization; to implement this concept, the reliability design method is employed, and the target reliability for seismic buckling of the reactor vessel is derived from nuclear plant safety goals. Input data for reliability evaluation, such as distribution type, mean value, and standard deviation of random variables, are also prepared. Seismic hazard is considered to evaluate uncertainty of seismic load. Minimum wall thickness required to achieve the target reliability is evaluated, and is found to be less than that determined from a conventional deterministic design method. Furthermore, the influence of each random variable on the evaluation is investigated, and it is found that the seismic load has a significant impact.

Source term uncertainty analysis; Probabilistic approaches and applications to a BWR severe accident

Zheng, X.; Ito, Hiroto; Tamaki, Hitoshi; Maruyama, Yu

Mechanical Engineering Journal (Internet), 2(5), p.15-00032_1 - 15-00032_14, 2015/10

http://doi.org/10.1299/mej.15-00032

ROSA/LSTF experiment on a PWR station blackout transient with accident management measures and RELAP5 analyses

Takeda, Takeshi; Otsu, Iwao

Mechanical Engineering Journal (Internet), 2(5), p.15-00132_1 - 15-00132_15, 2015/10

http://doi.org/10.1299/mej.15-00132

Investigation of the relocation behavior in core structures under severe accident condition by the JUPITER code

Yamashita, Susumu; Tokushima, Kazuyuki; Kurata, Masaki; Takase, Kazuyuki; Yoshida, Hiroyuki

Nihon Kikai Gakkai Dai-28-Kai Keisan Rikigaku Koenkai Rombunshu (CD-ROM), 3 Pages, 2015/10

no abstracts in English

Development of a measurement system for the determination of () cross-sections using multi-nucleon transfer reactions

Makii, Hiroyuki; Ota, Shuya*; Ishii, Tetsuro; Wakabayashi, Yasuo*; Furutaka, Kazuyoshi; Nishio, Katsuhisa; Nishinaka, Ichiro; Chiba, Satoshi; Igashira, Masayuki*; Czeszumska, A.*

Nuclear Instruments and Methods in Physics Research A, 797, p.83 - 93, 2015/10

https://doi.org/10.1016/j.nima.2015.05.005

We have installed new experimental apparatus to measure rays from highly excited states populated by the multi-nucleon transfer reactions with heavy-ion projectiles to determine the () cross sections by means of the surrogate reaction method. Apparatus consists of two anti-Compton LaBr(Ce) spectrometers to measure the rays and a Si - detector system to detect outgoing projectile-like particles. Reactions of 153-MeV O beams with Gd and Gd targets were used to study the performance of apparatus. By using the LaBr(Ce) scintillators with relatively large volume (101.6 mm in diameter and 127 mm in length), we have successfully measured rays from the compound nuclei, which have excitation energy above neutron separation energy, populated by Gd(O, O)Gd and Gd(O, O)Gd two-neutron transfer reactions. The present study has demonstrated high capability of apparatus to measure the de-excitation rays in the compound nuclei produced by the multi-nucleon transfer reactions for determination of the () cross sections by using the surrogate reaction method.

Mechanisms of increasing of the magnetic alloy core shunt impedance by applying a transverse magnetic field during annealing

Nomura, Masahiro; Shimada, Taihei; Tamura, Fumihiko; Yamamoto, Masanobu; Hara, Keigo*; Hasegawa, Katsushi*; Omori, Chihiro*; Toda, Makoto*; Yoshii, Masahito*

Nuclear Instruments and Methods in Physics Research A, 797, p.196 - 200, 2015/10

https://doi.org/10.1016/j.nima.2015.06.061

In the J-PARC synchrotrons, Magnetic Alloy (MA) cores loaded RF cavities are employed to achieve a high field gradient. We are successful to increase the shunt impedance of the MA cores for the Main Ring synchrotron RF cavities by applying a transverse magnetic field during annealing. The shunt impedances of the cores with transverse field annealing are around 50% higher than the cores without one. By applying the transverse magnetic field during annealing, the magnetization processes occur by mainly magnetization rotations, and consequently the core loss is reduced and the relative complex permeability shows an excellent frequency behavior. The MA core shunt impedance is increased by those improvements of the magnetic properties.

Development of hydrogen behavior simulation code system

Terada, Atsuhiko; Matsumoto, Masaaki*; Sugiyama, Hitoshi*; Kamiji, Yu; Hino, Ryutaro

Proceedings of 6th International Conference on Hydrogen Safety (ICHS 2015) (CD-ROM), 11 Pages, 2015/10

To improve the safety performance of the Nuclear Power Station, especially on the hydrogen safety under severe accident conditions, a simulation code system has been developed to analyze hydrogen behavior including diffusion, combustion, explosion and structural integrity evaluation. This developing system consists of CFD and FEM tools in order to support various hydrogen user groups consisting of students, researchers and engineers. Preliminary analytical results obtained with above mentioned tools, especially with open source codes including buoyancy turbulent model and condensation model, agreed well with the existing test data.

Thermal equilibrium and prehydration processes of electrons injected into liquid water calculated by dynamic Monte Carlo method

Kai, Takeshi; Yokoya, Akinari; Ukai, Masatoshi*; Fujii, Kentaro; Watanabe, Ritsuko

Radiation Physics and Chemistry, 115, p.1 - 5, 2015/10

https://doi.org/10.1016/j.radphyschem.2015.05.021

Role of secondary electrons on DNA damage have not been understood sufficiently because there still exists a lack of study for thermalization process of an electron in liquid phase. We calculated thermalization lengths and spatial distributions of an electron in liquid water using cross sections for rotation and phonon excitations in a liquid phase. Obtained thermalization lengths are in good agreement with experimental results reported by literatures. Thermalization time was also estimated from time evolution of spatial distributions of the incident electron to be hundreds femtoseconds. From these results, we predict that thermalization and pre-hydration of electron might progress simultaneously. These electrons possibly cause damage in biological molecules in a cell. Particularly severe types of DNA damage consisting of proximately located multiple lesions are potentially induced by reaction of DNA with the thermalized electrons by dissociative electron transfer.

Fuel restructuring behavior analysis of MA-bearing MOX fuels irradiated in a fast reactor

Ozawa, Takayuki; Ikusawa, Yoshihisa; Kato, Masato

Transactions of the American Nuclear Society, 113(1), p.622 - 624, 2015/10

A recycle system for minor actinides (MAs), in which MAs are recycled by reprocessing and irradiating them in a fast reactor, is studied to reduce the degree of hazard and the amount of high-level radioactive wastes. MAs would be used as mixed oxide (MOX) fuels with plutonium and uranium in fast reactors. Since MA content of MA-bearing MOX (MA-MOX) to be used in fast reactors is assumed to reach 5 wt%HM, the effects on not only fuel properties but also fuel behaviors have to be estimated to use MA-MOX as fast reactor fuels. As the MOX fuels to be used will be irradiated at a comparably high linear power and the fuel center temperature would be assumed to be over 2,273 K during irradiation in the fast reactors, fuel restructuring would take place due to void migration towards the fuel center under the radial temperature gradient, and a central void would be formed. Since the fuel center temperature would be decreased by the effect of formation of the central void, the fuel restructuring is one of the most important behaviors for fast reactor fuels. In this study, the effect of MA content on fuel restructuring behavior was estimated from the results of irradiation experiments such as B11 and B14 performed in Joyo to study the irradiation behaviors of MA-MOX and the calculation results using a fuel restructuring model which can take into account MA-MOX dependence on vapor pressure.

Development of polymer gel dosimeter based on radiation-crosslinked hydroxypropyl cellulose gel

Hiroki, Akihiro

Cellulose Communications, 22(3), p.143 - 145, 2015/09

http://ci.nii.ac.jp/naid/40020576977

no abstracts in English

Status of decommissioning of the Plutonium Fuel Fabrication Facility and R&Ds of dismantling technologies for gloveboxes

Kimura, Yasuhisa; Hirano, Hiroshi; Watahiki, Masatoshi; Kuba, Meiji; Ishikawa, Shinichiro

Dekomisshoningu Giho, (52), p.45 - 54, 2015/09

http://ci.nii.ac.jp/naid/40020624160

The Plutonium Fuel Fabrication Facility (PFFF) of the Japan Atomic Energy Agency is now in its decommissioning phase. In the PFFF, terminated gloveboxes have been dismantled. Gloveboxes to be dismantled are surrounded by a plastic enclosure to prevent contamination from being spread into process room. Dismantling operations for gloveboxes are performed manually by workers, each wearing an air-feed suit. However, the mental and physical loads placed on workers wearing the air-feed suits are intensively high. Therefore, R&Ds on new dismantling technologies including utilization of heavy machines covered with plastic enclosure for anti-contamination have been started to reduce the potential risks associated with workers and decommissioning costs. In this paper, the status of decommissioning of the PFFF and the overview of developed dismantling technologies for -tight gloveboxes are described.

Radionuclide transport behavior

Hidaka, Akihide

Enerugi Rebyu, 35(9), p.20 - 24, 2015/09

http://ci.nii.ac.jp/naid/40020565747

Operation of nuclear power plant causes accumulation of radionuclides in fuel rods as a result of nuclear fission of uranium and plutonium. During severe accidents, large amount of radionuclides are released from fuel and transport in the reactor coolant system and/or the containment. When the containment fails or its confinement function is lost, radionuclides could be released into the environment. Meanwhile, radionuclides can be removed by condensation onto wall, natural deposition such as gravitational settling, the engineered safety features (ESF) such as containment spray and so on. After various processes described above, the species, amounts and timing of radionuclide released into the environment is called source terms. The behavior of radionuclide can be described mechanistically by condensation or evaporation of gaseous radionuclide, deposition, growth and removal of aerosol by ESF. Present paper summarizes the radionuclide behavior during severe accidents.

On the dynamical approach of quantitative radiation biology

Ouchi, Noriyuki

Evolution of Ionizing Radiation Research, p.41 - 62, 2015/09

https://doi.org/10.5772/60859

Quantitative approach in radiation biology based on the clonogenic method and obtained cell survival curves as a dose-response relationship, are introduced. Generally, cell survival curves seem to have a universality on its function, i.e. functional form of survival curve seems to be unchanged under various conditions including different species. Various factors affecting the radiosensitivity have been introduced to find macroscopic nature of living organisms. Many mathematical models describing cell survival curves have been presented, however, functional form of cell survival curves derived from, based on biological mechanism does not yet exist. Finally, the possibility that the structural change of chromosome affects the repair process is discussed.

Summaries of the disposal business of low level radioactive waste arising from research, industrial and medical facilities

Sakamoto, Yoshiaki

Genkan Senta Topikkusu, (115), p.2 - 12, 2015/09

http://www.rwmc.or.jp/library/file/topicsNo.115.pdf

JAEA is going to push forward undergrounding disposal business of low level radioactive waste arising from the research facilities etc. in our country. The conceptual design of the trench facilities and the concrete pit facilities was carried out for total approximately 600,000 of drums as 200L drum of LLW in operation period of 50 years. In this lecture, outline of the disposal business and research activities about durability of a geomembrane lines for trench disposal facility and waste confirmation technology will be presented.

Application of health effect model of NUREG/CR-4214 to the Japanese population and comparison with a latest model

Takahara, Shogo; Iijima, Masashi; Shimada, Kazumasa

Hoken Butsuri, 50(3), p.172 - 181, 2015/09

Radiocarbon, carbon-14

Atarashi-Andoh, Mariko

Hosha Kagaku No Jiten, p.215 - 216, 2015/09

no abstracts in English

Nuclear reactions and reactivity control in light water reactor

Okumura, Keisuke

Hosha Kagaku No Jiten, p.228 - 230, 2015/09

As an interpretive article about the nuclear reaction and reactivity control in light water reactors, first, the base items, such as a nuclear reactions, neutron multiplication factor, criticality, and reactivity, are explained, and the concrete methods of the reactivity control in PWR and BWR are explained plainly.

Environmental radiation monitoring

Takeishi, Minoru

Hosha Kagaku No Jiten, p.200 - 201, 2015/09

I described an environmental radiation monitoring in the radiochemical dictionary. The purpose of an environmental radiation monitoring is to evaluate radiation effect for the public through the measurements of radiation and radioactivity in the environment. There are two different situations regarding environmental radiation monitoring, in normal and in emergency. The purpose, method and notice are described in this explanation.

Measurement of transient photo-induced changes in thin films at J-PARC; Time-resolved neutron reflectivity measurements of silver photo-diffusion into Ge-chalcogenide films

Sakaguchi, Yoshifumi*; Asaoka, Hidehito; Uozumi, Yuki; Kawakita, Yukinobu; Ito, Takayoshi*; Kubota, Masato; Yamazaki, Dai; Soyama, Kazuhiko; Ailavajhala, M.*; Wolf, K.*; et al.

JPS Conference Proceedings (Internet), 8, p.031023_1 - 031023_6, 2015/09

https://doi.org/10.7566/JPSCP.8.031023

We report recent results of time-resolved neutron reflectivity measurements for silver photo-diffusion into GeS (x=0.20, 0.33, 0.40) films performed on BL17 (SHARAKU). It is well known that silver diffuses into Ge-chalcogenide layer by visible light exposure with a distinct diffusion front, where the silver concentration abruptly drops off. Using an event recording system at the Materials and Life Science Experimental Facility, neutron reflectivity profiles were collected with a time-resolution of 30 seconds in the shortest case. It was found from the measurements that a relatively stable Ag-rich phase in the reaction layer is firstly formed, and then, slower diffusion occurs at the interface between Ag-rich and Ag-poor layers. Fourier transform analysis showed that the position of the interface is essentially fixed. This result is in contrast to the previously reported model of silver diffusion that postulates a mechanism involving progression of the diffusion front. The results of the measurements on Ag/Ge-Se films performed on the INTER instrument at ISIS are also reported.

Background caused by continuously emitted high-energy neutrons at the chopper spectrometer 4SEASONS

Kajimoto, Ryoichi; Nakamura, Mitsutaka; Inamura, Yasuhiro; Kamazawa, Kazuya*; Ikeuchi, Kazuhiko*; Iida, Kazuki*; Ishikado, Motoyuki*; Nakajima, Kenji; Harada, Masahide; Arai, Masatoshi

JPS Conference Proceedings (Internet), 8, p.036001_1 - 036001_6, 2015/09

https://doi.org/10.7566/JPSCP.8.036001

Neutron diffraction study of 1D quantum spin system LiZrCuO with incommensurate magnetic structure

Yasui, Yukio*; Igawa, Naoki; Kakurai, Kazuhisa

JPS Conference Proceedings (Internet), 8, p.034012_1 - 034012_6, 2015/09

https://doi.org/10.7566/JPSCP.8.034012

Magnetic structure has been studied by using neutron diffraction for quasi one-dimensional quantum spin system LiZrCuO with CuO ribbon chains. The CuO ribbon system LiZrCuO exhibits the antiferromagnetic transition at T 7 K, however, the magnetic transition is not accompanied with ferroelectricity. At 3K, we observed magnetic superlattice reflections at Q = (0, k, l) and (h, 0, l) (h, k and l = even) with 0.488 by the powder neutron diffraction. By the combined studies of neutron diffraction and magnetization data, the magnetic structure of LiZrCuO is proposed. On the bases of the obtained data, reasons for absence of ferroelectricity in LiZrCuO are discussed.

A Crafty utilization of intermediate-angle neutron scattering and contrast variation by water-exchange to study the microstructure of microbial cellulose

Zhao, Y.; Koizumi, Satoshi*; Kondo, Tetsuo*

JPS Conference Proceedings (Internet), 8, p.033002_1 - 033002_6, 2015/09

https://doi.org/10.7566/JPSCP.8.033002

Catchment-scale distribution of radiocesium air dose rate in a mountainous deciduous forest and its relation to topography

Atarashi-Andoh, Mariko; Koarashi, Jun; Takeuchi, Erina; Tsuzuki, Katsunori; Nishimura, Shusaku; Matsunaga, Takeshi

Journal of Environmental Radioactivity, 147, p.1 - 7, 2015/09

AA2014-0585.pdf:2.18MB

https://doi.org/10.1016/j.jenvrad.2015.05.004

We collected a large amount of radiocesium air dose rate data by mountain-walking with a small -ray survey system, KURAMA-II, to create an air dose rate map of a mountainous deciduous forest that received radiocesium from the Fukushima Dai-ichi Nuclear Power Plant accident. Measurements were conducted in a small stream catchment 0.6 km in size in August and September 2013, and the relationship between air dose rates and the mountainous topography was examined. Air dose rates increased with elevation, suggesting that more radiocesium was deposited on ridges, and that it had remained there for 2.5 years with no significant migration due to soil erosion or water drainage. Slope aspect also strongly affected air dose rates. By the continuous measurement using KURAMA-II, we describe the variation in air dose rates in a mountainous area and suggest that it is important to consider topography when selecting sampling points to estimating dose rates or contaminant deposition.

Feasibility studies on electrochemical recovery of uranium from solid wastes contaminated with uranium using 1-butyl-3-methylimidazorium chloride as an electrolyte

Ohashi, Yusuke; Harada, Masayuki*; Asanuma, Noriko*; Ikeda, Yasuhisa*

Journal of Nuclear Materials, 464, p.119 - 127, 2015/09

https://doi.org/10.1016/j.jnucmat.2015.04.024

In order to examine feasibility of the electrochemical deposition method for recovering uranium from the solid wastes contaminated with uranium using ionic liquid as electrolyte, we have studied the electrochemical behavior of each solution prepared by soaking the spent NaF adsorbents and the steel waste contaminated with uranium in BMICl (1-butyl-3-methyl- imidazolium chloride). The uranyl(VI) species in BMICl solutions were found to be reduced to U(V) irreversibly around -0.8 to -1.3 V vs. Ag/AgCl. Based on the electrochemical data, we have performed potential controlled electrolysis of each solution at -1.5 V vs. Ag/AgCl. Black deposit was obtained, and their composition analyses suggest that the deposit is the mixtures of U(IV) and U(VI) compounds containing O, F, Cl, and N elements. From the present study, it is expected that the solid wastes contaminated with uranium can be decontaminated by treating them in BMICl and the dissolved uranium species are recovered electrolytically.

Study on application of kriging to evaluation of radioactivity concentration for ensuring compliance with the criterion of site release

Ishigami, Tsutomu; Shimada, Taro

Journal of Nuclear Science and Technology, 52(9), p.1186 - 1204, 2015/09

https://doi.org/10.1080/00223131.2014.1001458

In the field of decommissioning of nuclear facilities, a reliable method for ensuring compliance with the criterion of site release is an important technical issue to be resolved in Japan. Considering that kriging can consider the spatial correlation of radioactivity concentrations, we propose a method of applying kriging to ensure compliance with the site release criterion. Estimated radioactivity concentrations exhibit uncertainty, which results in a certain probability of the occurrence of decision errors regarding site release. We describe a method for calculating the uncertainty and establish a minimum number of measurement points required. We applied the proposed method and a conventional statistical method to two sample cases. It was observed that the proposed method appropriately estimated the mean radioactivity concentration and led to an efficient measurement requiring fewer measurement points relative to the conventional method when spatial correlation existed.

Corrigendum; Pulse pileup correction in the presence of a large low-energy background [J. Nucl. Sci. Technol. 2015; 52: 426-433]

Angell, C.

Journal of Nuclear Science and Technology, 52(9), P. 1205, 2015/09

https://doi.org/10.1080/00223131.2015.1055079

Theoretical study of -edge resonant inelastic X-ray Scattering in LaCuO on the basis of detailed electronic band structure

Nomura, Takuji

Journal of the Physical Society of Japan, 84(9), p.094704_1 - 094704_13, 2015/09

https://doi.org/10.7566/JPSJ.84.094704

We study theoretically resonant inelastic X-ray scattering (RIXS) at the Cu -edge in a typical parent compound of high- cuprate superconductors LaCuO on the basis of a detailed electronic band structure. We construct a realistic and precise tight-binding model by employing the maximally-localized Wannier functions derived from a first-principles electronic structure calculation, and then take account of the Coulomb repulsion between electrons at each Cu site. The antiferromagnetic ground state is described within the Hartree-Fock approximation, and take account of electron correlations in the intermediate states of RIXS within the random-phase approximation (RPA). Calculated RIXS spectra agree well with the experimentally observed features including low-energy magnon excitation, - excitations, and charge-transfer excitations, over a wide excitation-energy range. In particular, we stress the importance of photon polarization dependence: the intensity of magnon excitation and the spectral structure of - excitations depend significantly not only on the polarization direction of incident incoming photons but also that of outgoing photons.

First-principles study of antimony doping effects on the iron-based superconductor CaFe(SbAs)

Nagai, Yuki; Nakamura, Hiroki; Machida, Masahiko; Kuroki, Kazuhiko*

Journal of the Physical Society of Japan, 84(9), p.093702_1 - 093702_4, 2015/09

https://doi.org/10.7566/JPSJ.84.093702

no abstracts in English

Josephson effect and point-contact spectroscopy studies of the anomaly observed in the superconducting state of the heavy-fermion compound UBe

Gochi, Jun; Sumiyama, Akihiko*; Yamaguchi, Akira*; Motoyama, Gaku*; Haga, Yoshinori; Onuki, Yoshichika

Journal of the Physical Society of Japan, 84(9), p.094714_1 - 094714_5, 2015/09

https://doi.org/10.7566/JPSJ.84.094714

The Promising features of new nano liquid metals; Liquid sodium containing titanium nanoparticles (LSnanop)

Itami, Toshio*; Saito, Junichi; Ara, Kuniaki

Metals, 5(3), p.1212 - 1240, 2015/09

https://doi.org/10.3390/met5031212

A new kind of suspension liquid was developed by dispersing Ti nanoparticles (10 nm) in liquid Na, which was then determined by TEM (transmission electron microscopy) analysis. The volume fraction was estimated to be 0.0088 from the analyzed Ti concentration (2 at.%) and the densities of Ti and Na. This suspension liquid, Liquid Sodium containing nanoparticles of titanium (LSnanop), shows, despite only a small addition of Ti nanoparticles, many striking features, namely a negative deviation of 3.9% from the ideal solution for the atomic volume, an increase of 17% in surface tension, a decrease of 11% for the reaction heat to water, and the suppression of chemical reactivity to water and oxygen. The decrease in reaction heat to water seems to be derived from the existence of excess cohesive energy of LSnanop. The excess cohesive energy was discussed based on simple theoretical analyses, with particular emphasis on the screening effect. The suppression of reactivity is discussed with the relation to the decrease of heat of reaction to water or the excess cohesive energy, surface tension, the action as a plug of Ti oxide, negative adsorption on the surface of LSnanop, and percolation.

Activity to establish the guideline for credibility assessment of nuclear simulations in the Atomic Energy Society of Japan

Tanaka, Masaaki

Nihon Genshiryoku Gakkai Keisan Kagaku Gijutsu Bukai Nyusu Reta (Internet), (24), p.16 - 28, 2015/09

http://csed.sakura.ne.jp/archives/1256

In order to enhance the simulation credibility, it is necessary to establish the procedure on verification and validation including the estimation of the modeling uncertainty. Lessons learned from the Fukushima Daiichi NPP Accident have indicated that it was important to recognize the credibility of the simulation. By putting forward to standardize the procedure on verification and validation including the estimation of the modeling uncertainty, it is expected to establish the basis of the simulation technology to realize the world highest level of nuclear safety and continuous improvement. The recent activity in the Atomic Energy Society of Japan (AESJ) for the guideline establishment is introduced.

Investigation of single-cycle separation process based on forward and backward extractions of actinides and fission products

Sasaki, Yuji; Tsubata, Yasuhiro; Shirasu, Noriko; Morita, Keisuke; Suzuki, Tomoya

Nihon Genshiryoku Gakkai Wabun Rombunshi, 14(3), p.202 - 212, 2015/09

https://doi.org/10.3327/taesj.J14.042

We have been developing the new partitioning method of high-level radioactive waste by single-cycle extraction process. This process is composed of extraction of actinides (An) and fission products (FP, e.g., Pd, Ru, Mo and Tc), and mutual separation by back-extraction. The extractant employed in this process is required to extract soft, hard acid metals and oxonium anions simultaneously. The NTAamide (hexaoctyl-nitrilotriacetamide) is one of the candidate extractants. After extraction of An and FP, the mutual separation by back-extraction should be set up. Pd and Ru extracted by NTAamide can be back-extracted by complexing agents such as thiourea, systeine, diethylenetriamine, and trisaminoethylamine, and the back-extraction of Mo can be performed by methylimino-diethylacetamide (MIDEA), NTAamide(C2) and iminodimethylphosphoric acid, and Re can be done by aqueous phase with high pH.

Experiment and analytical studies on bubbly flow behavior around a spacer in circular duct

Sakka, Taku*; Jiao, L.; Uesawa, Shinichiro; Yoshida, Hiroyuki; Takase, Kazuyuki

Nihon Kikai Gakkai 2015-Nendo Nenji Taikai Koen Rombunshu (DVD-ROM), 5 Pages, 2015/09

no abstracts in English

Magnetization plateaus by reconstructed quasispinons in a frustrated two-leg spin ladder under a magnetic field

Sugimoto, Takanori*; Mori, Michiyasu; Toyama, Takami*; Maekawa, Sadamichi

Physical Review B, 92(12), p.125114_1 - 125114_6, 2015/09

AA2015-0451.pdf:0.43MB

https://doi.org/10.1103/PhysRevB.92.125114

High intensity single bunch operation with heavy periodic transient beam loading in wide band RF cavities

Tamura, Fumihiko; Hotchi, Hideaki; Schnase, A.*; Yoshii, Masahito*; Yamamoto, Masanobu; Omori, Chihiro*; Nomura, Masahiro; Toda, Makoto*; Shimada, Taihei; Hasegawa, Katsushi*; et al.

Physical Review Special Topics; Accelerators and Beams, 18(9), p.091004_1 - 091004_8, 2015/09

https://doi.org/10.1103/PhysRevSTAB.18.091004

The RCS in the J-PARC was originally designed to accelerate two high intensity bunches, while some of neutron experiments in the MLF and a muon experiment using MR beams require a single bunch operation mode. The beam intensity in the single bunch operation has been limited by longitudinal beam losses due to the rf bucket distortions by the wake voltage of the odd harmonics in the wide band MA cavities. We installed an additional rf feedforward system to compensate the wake voltages of the odd harmonics (h=1,3,5). The longitudinal beam losses during the single bunch acceleration disappeared with feedforward for the odd harmonics. We also confirmed that the beam quality in the single bunch acceleration are similar to that of the normal operation with two bunches. Thus, high intensity single bunch acceleration at the intensity of 2.310 protons per bunch has been achieved in the J-PARC RCS.

Observation of new neutron-deficient isotopes with Z92 in multinucleon transfer reactions

Devaraja, H. M.*; Heinz, S.*; Beliuskina, O.*; Comas, V. F.*; Hofmann, S.*; Hornung, C.*; Mnzenberg, G.*; Nishio, Katsuhisa; Ackermann, D.*; Gambhir, Y. K.*; et al.

Physics Letters B, 748, p.199 - 203, 2015/09

AA2015-0304.pdf:0.78MB

https://doi.org/10.1016/j.physletb.2015.07.006

Formative mechanism of inhomogeneous distribution of fractures, an example of the Toki Granite, Central Japan

Sasao, Eiji; Yuguchi, Takashi*; Ito, Yasuto*; Inoue, Takashi*; Ishibashi, Masayuki

Proceedings of 10th Asian Regional Conference of International Association for Engineering Geology and the Environment (IAEG ARS 2015) (USB Flash Drive), 6 Pages, 2015/09

Understanding of the fracture network is important for disposal of high-level radioactive waste. We present our hypothesis on the formative mechanism of inhomogeneous distribution of fracture in the Toki Granite. In the Toki Granite, low- and high-angle fractures are abundant at the shallower part, while less at the deeper part where high-angle fracture is dominant. Distribution of the high-angle fracture is inhomogeneous. Thermochronological study revealed that the rapid cooling occurred at the early stage of granite formation. Paleomagnetic directions of the intact granite were dispersed. This suggests granite was plastically deformed during rapid cooling period. The rapid cooling might cause inhomogeneous distribution of cooling strain. When the granite reached to brittle deformation field, inhomogeneous fracture distribution was formed by the inhomogeneous strain. If so, recognition of the cooling history is essential to understand the distribution of the fracture network.

Investigation of phosphor materials for the real-time measurement of the transverse intensity distribution of large-area ion beams at the JAEA AVF cyclotron facility

Yuri, Yosuke; Yuyama, Takahiro; Ishizaka, Tomohisa; Koka, Masashi; Yamada, Naoto

Proceedings of 12th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.420 - 423, 2015/09

http://www.pasj.jp/web_publish/pasj2015/proceedings/PDF/WEP0/WEP011.pdf

no abstracts in English

Study of shunt impedance of the FT3L magnetic alloy core

Nomura, Masahiro; Yamamoto, Masanobu; Shimada, Taihei; Tamura, Fumihiko; Omori, Chihiro*; Toda, Makoto*; Hasegawa, Katsushi*; Hara, Keigo*; Yoshii, Masahito*

Proceedings of 12th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.1096 - 1110, 2015/09

http://www.pasj.jp/web_publish/pasj2015/proceedings/PDF/THP0/THP053.pdf

We are successful in increasing the shunt impedance of the MA cores by applying a transverse magnetic field during annealing. In this paper, we discuss the effects of transverse field annealing on the MA core shunt impedance by comparing two kinds of MA cores, those are the FT3M core that is annealed without any magnetic fields and the FT3L core that is annealed with a transverse magnetic field. We also discuss the shunt impedance of the MA core when the magnetization processes are governed by ideal magnetization rotations. To understand the ribbon thickness and the permeability dependences of the shunt impedance intuitively, we represent the shunt impedance as the resistance of the closed rectangular loop through which the eddy current flows.

Influence of contaminants from spent fuel pools at the Fukushima Daiichi Nuclear Power Station on the reprocessing process

Aihara, Haruka; Kitawaki, Shinichi; Nomura, Kazunori; Taguchi, Katsuya

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.1076 - 1083, 2015/09

Application of turbidity measurement for evaluation of two-phase separation in ,-dialkylamides-nitric acid systems

Tsutsui, Nao; Ban, Yasutoshi; Hakamatsuka, Yasuyuki; Urabe, Shunichi; Matsumura, Tatsuro

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.1153 - 1157, 2015/09

,-Dialkylamides are promising alternative extractants to tri--butyl phosphate in the reprocessing of spent nuclear fuels, but the two-phase separation between their organic and aqueous phases has not been evaluated quantitatively. ,-Di(2-ethylhexyl)-2,2-dimethylpropanamide (DEHDMPA) in -dodecane were agitated with uranyl nitrate-containing nitric acid, and their turbidities and their uranium distribution ratios were measured with respect to the time for the quantitative evaluation. Increasing DEHDMPA, uranium, and nitric acid concentrations enhanced turbidities. Although turbidities decreased with respect to the time, uranium distribution ratios slightly changed, indicating the observed turbidities did not affect these uranium distribution ratios significantly. Therefore, DEHDMPA may act as suitable extractant for uranium in nitric acid from two-phase separation viewpoint, and turbidity may be an indicator for extractant performance evaluation.

Development of a fast reactor for minor actinides transmutation, 1; Overview and method development

Takeda, Toshikazu*; Usami, Shin; Fujimura, Koji*; Takakuwa, Masayuki*

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.560 - 566, 2015/09

The Ministry of Education, Culture, Sports, Science and Technology in Japan has launched a national project entitled "technology development for the environmental burden reduction" in 2013. The present study is one of the studies adopted as the national project. The objective of the study is the efficient and safe transmutation and volume reduction of minor actinides with long-lived radioactivity and high decay heat contained in high level radioactive wastes by using sodium cooled fast reactors. We are developing MA transmutation core concepts which harmonize efficient MA transmutation with core safety. To accurately design the core concepts we have improved calculation methods for estimating the transmutation rate of individual MA nuclides, and estimating and reducing uncertainty of MA transmutation. The overview of the present project is first described. The method improvement is presented with numerical results for a minor-actinide transmutation fast reactor.

Development of a fast reactor for Minor Actinides (MAs) transmutation, 3; Evaluation of measurement data with MA transmutation

Sugino, Kazuteru; Takeda, Toshikazu*

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.573 - 581, 2015/09

Development of a fast reactor for minor actinides transmutation, 2; Study on the MA transmutation core concepts

Fujimura, Koji*; Oki, Shigeo; Takeda, Toshikazu*

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.592 - 598, 2015/09

Conceptual study of a plutonium burner high temperature gas-cooled reactor with high nuclear proliferation resistance

Goto, Minoru; Demachi, Kazuyuki*; Ueta, Shohei; Nakano, Masaaki*; Honda, Masaki*; Tachibana, Yukio; Inaba, Yoshitomo; Aihara, Jun; Fukaya, Yuji; Tsuji, Nobumasa*; et al.

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.507 - 513, 2015/09

A concept of a plutonium burner HTGR named as Clean Burn, which has a high nuclear proliferation resistance, had been proposed by Japan Atomic Energy Agency. In addition to the high nuclear proliferation resistance, in order to enhance the safety, we propose to introduce PuO-YSZ TRISO fuel with ZrC coating to the Clean Burn. In this study, we conduct fabrication tests aiming to establish the basic technologies for fabrication of PuO-YSZ TRISO fuel with ZrC coating. Additionally, we conduct a quantitative evaluation of the security for the safety, a design of the fuel and the reactor core, and a safety evaluation for the Clean Burn to confirm the feasibility. This study is conducted by The University of Tokyo, Japan Atomic Energy Agency, Fuji Electric Co., Ltd., and Nuclear Fuel Industries, Ltd. It was started in FY2014 and will be completed in FY2017, and the first year of the implementation was on schedule.

Accumulation of gadolinium isotopes in used nuclear fuel

Suyama, Kenya; Kashima, Takao

Proceedings of International Conference on Nuclear Criticality Safety (ICNC 2015) (DVD-ROM), p.273 - 282, 2015/09

In the technical development of the criticality safety control of the fuel debris of Fukushima accident in Japan, there have been a discussion on a possibility of adopting BUC with FP. The Expert Group on Burnup Credit Criticality Safety (EGBUC) under the Working Party on Nuclear Criticality Safety (WPNCS) in OECD/NEA Nuclear Science Committee had carried out an international burnup calculation benchmark "Phase-IIIB" and "Phase-IIIC" for BWR fuel assemblies. In these benchmarks the difference of the calculation results of Gd among the participants obtained keen interests because it showed rather larger difference among the participants. Authors has been carried out additional analyses on the accumulation of the gadolinium isotopes in the used nuclear fuel during the burnup. Without cooling time, the assembly-averaged amount of Gd against the burnup value depends on the burnout property of gadolinium in the burnable poison rods. However, after few year cooling time, Gd increase drastically by the decay of Eu. In this case, the amount of gadolinium isotopes in the burnable poison rods has less importance. It means that the adopted parameters and data concerning the Eu generation have much more importance than the burnup treatment of the burnable poison rods for better prediction of Gd.

Study on criticality control of fuel debris by Japan Atomic Energy Agency to support Nuclear Regulation Authority of Japan

Tonoike, Kotaro; Yamane, Yuichi; Umeda, Miki; Izawa, Kazuhiko; Sono, Hiroki

Proceedings of International Conference on Nuclear Criticality Safety (ICNC 2015) (DVD-ROM), p.20 - 27, 2015/09

From the viewpoint of safety regulation, criticality control of the fuel debris in the Fukushima Daiichi Nuclear Power Station would be a risk-informed control to mitigate consequences of criticality events, instead of a deterministic control to prevent such events. The Nuclear Regulation Authority of Japan has set up a research and development program to tackle this challenge. The Nuclear Safety Research Center of Japan Atomic Energy Agency, commissioned by the authority, has launched activities such as computations of criticality characteristics of the fuel debris, development of criticality risk assessment method, and preparation of criticality experiments to support them.

Live-cell imaging study of mitochondrial morphology in mammalian cells exposed to X-rays

Noguchi, Miho; Kanari, Yukiko; Yokoya, Akinari; Narita, Ayumi; Fujii, Kentaro

Radiation Protection Dosimetry, 166(1-4), p.101 - 103, 2015/09

https://doi.org/10.1093/rpd/ncv157

Real-time observation of irradiated HeLa-cell modified by fluorescent ubiquitination-based cell-cycle indicator using synchrotron X-ray microbeam

Narita, Ayumi; Kaminaga, Kiichi; Yokoya, Akinari; Noguchi, Miho; Kobayashi, Katsumi*; Usami, Noriko*; Fujii, Kentaro

Radiation Protection Dosimetry, 166(1-4), p.192 - 196, 2015/09

https://doi.org/10.1093/rpd/ncv156

For the knowledge about irradiation effects of mammalian cells depending on the cell cycle, most of them had been analyzed by statistical approches. Our purpose is to establish the method for real-time observation of irradiated cells under a microscope. Fluorescent ubiquitination-based cell cycle indicator (FUCCI) human cancer (HeLa) cells (red indicates G1; green, S/G2) were exposed to a synchrotron X-ray microbeam. Cells in either G1 or S/G2 were selectively irradiated according to cell color observed in the same microscopic field in a culture dish. Time-lapse micrographs of the irradiated cells were acquired for 24 h after irradiation. The cell cycle was strongly arrested by irradiation at S/G2 and never progressed to G1. In contrast, cells irradiated at G1 progress to S/G2 with a similar time course as non-irradiated control cells. These results show single FUCCI cell exposure and live cell imaging are powerful methods for studying radiation effects on the cell cycle.

Chemistry of the heaviest elements

Nagame, Yuichiro

Science and Culture, 81(9-10), p.248 - 258, 2015/09

http://www.scienceandculture-isna.org/sept-oct-2015/08%20Art_Chemistry_of_the_Heaviest%20Metals_by_Yuichiro%20Nagame_Pg.248.pdf

Surface stress measurement of Si(111) 77 reconstruction by comparison with hydrogen-terminated 11 surface

Asaoka, Hidehito; Uozumi, Yuki

Thin Solid Films, 591(Part B), p.200 - 203, 2015/09

We have focused on measurements of the surface stress in Si(111) as a function of 77 reconstruction by comparison with the hydrogen (H)-terminated Si(111) 11 surface. In order to obtain information on both the surface stress and the surface reconstruction simultaneously, we have combined the surface-curvature and the reflection-high-energy-electron-diffraction instrumentations in an identical ultrahigh vacuum system. The stress evolution shows a decrease of tensile stress corresponding to the formation of H-termination at the beginning of the atomic H exposure of Si(111) 77 surface. After the above treatment, a complete transformation of the surface structure occurs from the reconstructed surface to the 11 one. As a result, we find the H-terminated Si(111) 11 surface releases 1.7 N/m (=J/m), or (1.4 eV/(11 unit cell)), of the surface energy from the strong tensile Si(111) 77 reconstruction.

Calculation of reactor kinetics parameters with Monte Carlo differential operator sampling

Nagaya, Yasunobu

Annals of Nuclear Energy, 82, p.226 - 229, 2015/08

https://doi.org/10.1016/j.anucene.2014.08.064

The methods to calculate the kinetics parameters of and with the differential operator sampling have been reviewed. The comparison of the results obtained with the differential operator sampling and iterated fission probability approaches has been performed. It is shown that the differential operator sampling approach gives the same results as the iterated fission probability approach within the statistical uncertainty. In addition, the prediction accuracy of the evaluated nuclear data library JENDL-4.0 for the measured values is also examined. It is shown that JENDL-4.0 gives a good prediction except for the uranium-233 systems. The present results imply the need for revisiting the uranium-233 nuclear data evaluation but detailed sensitivity analysis is required for further discussion.

Overview of particle and heavy ion transport code system PHITS

Sato, Tatsuhiko; Niita, Koji*; Matsuda, Norihiro; Hashimoto, Shintaro; Iwamoto, Yosuke; Furuta, Takuya; Noda, Shusaku; Ogawa, Tatsuhiko; Iwase, Hiroshi*; Nakashima, Hiroshi; et al.

Annals of Nuclear Energy, 82, p.110 - 115, 2015/08

https://doi.org/10.1016/j.anucene.2014.08.023

The general purpose Monte Carlo Particle and Heavy Ion Transport code System, PHITS, is being developed through a collaboration of several institutes in Japan and Europe. The Japan Atomic Energy Agency is responsible for managing the entire project. PHITS can deal with the transport of nearly all particles, including neutrons, protons, heavy ions, photons, and electrons, over wide energy ranges using various nuclear reaction models and data libraries. This paper briefly summarizes the physics models implemented in PHITS, and introduces some important functions useful for particular purposes, such as an event generator mode and beam transport functions.

Large-pore diameter nano-adsorbent and its application for rapid lead(II) detection and removal from aqueous media

Shahat, A.*; Awual, M. R.; Khaleque, M. A.*; Alam, M. Z.*; Naushad, M.*; Chowdhury, A. M. S*

Chemical Engineering Journal, 273, p.286 - 295, 2015/08

https://doi.org/10.1016/j.cej.2015.03.073

Hydrochemical disturbances measured in groundwater during the construction and operation of a large-scale underground facility in deep crystalline rock in Japan

Iwatsuki, Teruki; Hagiwara, Hiroki; Omori, Kazuaki; Munemoto, Takashi; Onoe, Hironori

Environmental Earth Sciences, 74(4), p.3041 - 3057, 2015/08

https://doi.org/10.1007/s12665-015-4337-3

Changes of hydrochemical condition resulting from large-scale underground facility construction to 500 m depth in sedimentary and granitic rock were evaluated at the Mizunami Underground Research Laboratory (MIU), Japan. The investigation of hydrochemical impact around the facility suggests that an understanding of hydrogeological structures, including hydrogeological compartments prior to facility construction and the locating of shafts/galleries in low permeability rock area is essential to minimize hydrochemical disturbances.

Physicochemical and ion-binding properties of highly aliphatic humic substances extracted from deep sedimentary groundwater

Saito, Takumi; Terashima, Motoki; Aoyagi, Noboru; Nagao, Seiya*; Fujitake, Nobuhide*; Onuki, Toshihiko

Environmental Science; Processes & Impacts, 17(8), p.1386 - 1395, 2015/08

https://doi.org/10.1039/C5EM00176E

The deep groundwater HSs were different from surface HSs, having high aliphaticities, sulfur contents, and small molecular sizes. The amounts of their acidic functional groups were comparable to or slightly larger than those of surface HSs; however, the magnitude of Cu binding to the deep groundwater HSs was smaller. The NICA-Donnan model attributed this to the binding of Cu to chemically homogeneous carboxylic-type sites via mono-dentate coordination at relatively low pH. The binding mode tended to shift to multi-dentate coordination with carboxylic-type and probably more heterogeneous alcoholic hydroxide-type groups at higher pH. This study shows the particularity of the deep groundwater HSs in terms of their physicochemical and ion-binding properties, compared with surface HSs.

High-Pressure Neutron Diffractometer PLANET

Hattori, Takanori

Hamon, 25(3), p.231 - 237, 2015/08

https://doi.org/10.5611/hamon.25.3_231

PLANET is a time-of-flight (TOF) neutron beamline dedicated to high-pressure experiments. By using several high-pressure devices, neutron diffraction patterns are obtainable at wide PT condition, ranging from 0-20 GPa and 77 K-2000 K. To obtain clean pattern, the beamline is equipped with the incident slits and receiving collimators to eliminate parasitic scattering from the high-pressure cell. The high performance of the diffractometer with the resolution (d/d = 0.6%) and the accessible d-spacing range (0.2-8.4 ) together with low-parasitic scattering characteristics enables precise structure determination of crystals and liquids even under high-pressure and high-temperature conditions.

Adsorption kinetics, isotherms, and thermodynamic studies for the adsorption of Pb and Hg metal ions from aqueous medium using Ti(IV) iodovanadate cation exchanger

Naushad, M.*; Alothman, Z. A.*; Awual, M. R.; Alam, M. M.*; Eldesoky, G. E.*

Ionics, 21(8), p.2237 - 2245, 2015/08

https://doi.org/10.1007/s11581-015-1401-7

Development of hydrophobic platinum catalyst for the effective collection of tritium in fusion plants

Iwai, Yasunori; Kubo, Hitoshi*; Oshima, Yusuke*

Isotope News, (736), p.12 - 17, 2015/08

http://www.jrias.or.jp/books/pdf/201508_TENBO_IWAI.pdf

We have successfully developed a new hydrophobic platinum catalyst for collecting tritium at nuclear fusion reactors. Catalysts used to collect tritium are called hydrophobic precious metal catalysts. In Japan, hydrophobic precious metal catalysts manufactured from polymers have been used for heavy water refinement.However, this catalyst has issues related to embrittlement to radiation and thermal stability. These technological issues needed to be solved to allow for its application to nuclear fusion reactors requiring further enrichment from highly-concentrated tritiated water. We developed a new method of manufacturing catalysts involving hydrophobic processing with an inorganic substance base. As a result, previous technological issues were able to be solved with the development of a catalyst that exhibited no performance degradation in response to radiation application of 530kGy, a standard for radiation resistance, and maintenance of thermal stability at over 600C, which is much higher than the 70C temperature that is normally used. The catalyst created with this method was also confirmed to have achieved the world's highest exchange efficiency, equivalent to 1.3 times the previously most powerful efficiency. The application of this catalyst to the liquid phase catalytic exchange process is expected to overcome significant technological hurdles with regards to improving the reliability and efficiency of systems for collecting tritium from tritiated water.

ICRP Publication 116 "Conversion Coefficients for Radiological Protection Quantities for External Radiation Exposures"; Summary

Endo, Akira

Isotope News, (736), p.34 - 37, 2015/08

http://www.jrias.or.jp/books/pdf/201508_TRACER_ENDO.pdf

Japanese translation of ICRP Publication 116 entitled "Conversion Coefficients for Radiological Protection Quantities for External Radiation Exposures" was published by the Japan Radioisotope Association in March 2015. The book gives fluence to dose conversion coefficients for both effective dose and organ absorbed doses for various types of external exposures, consistent with the 2007 Recommendations of the ICRP. A complete set of conversion coefficients is provided in an accompanying CD in ASCII format and Microsoft Excel software. This article overviews ICRP Publication 116 and its impact to practice of radiation protection.

Determination of the Compound Biological Effectiveness (CBE) factors based on the ISHIYAMA-IMAHORI deterministic parsing model with the dynamic PET technique

Ishiyama, Shintaro; Imahori, Yoshio*; Itami, Jun*; Koivunoro, H.*

Journal of Cancer Therapy, 6(8), p.759 - 766, 2015/08

https://doi.org/10.4236/jct.2015.68083

From the concentration of 10BPA drug was intravenously injected into the tumor and normal cells of brain tumor patients measured by dynamic PET method, the CBE factor for the BNCT treatment can be calculated by using ISHIYAMA-IMAHORI model.

Comparative modeling of an in situ diffusion experiment in granite at the Grimsel Test Site

Soler, J. M.*; Landa, J.*; Havlov, V.*; Tachi, Yukio; Ebina, Takanori*; Sardini, P.*; Siitari-Kauppi, M.*; Eikenberg, J.*; Martin, A. J.*

Journal of Contaminant Hydrology, 179, p.89 - 101, 2015/08

https://doi.org/10.1016/j.jconhyd.2015.06.002

Matrix diffusion is a key process for radionuclide retention in crystalline rocks. An in-situ diffusion experiment in granite matrix was performed at the Grimsel Test Site (Switzerland). Several tracers (HTO, Na, Cs) were circulated through a borehole and the decrease in tracer concentrations was monitored for 2.5 years. Then, the borehole section was overcored and the tracer profiles in the rock were analyzed. Transport distances in the rock were 20 cm for HTO, 10 cm for Na and 1 cm for Cs. The dataset was analyzed with diffusion-sorption models by different teams using different codes, with the goal of obtaining effective diffusivities (De) and rock capacity factors. There was a rather good agreement between the values from different teams, implied that De and capacity factors in the borehole damaged zone are larger than those in the bulk rock. However, HTO seems to display large discrepancies between measured and modeled results.

Radiocaesium activity concentrations in parmelioid lichens within a 60 km radius of the Fukushima Dai-ichi Nuclear Power Plant

Dohi, Terumi; Omura, Yoshihito*; Kashiwadani, Hiroyuki*; Fujiwara, Kenso; Sakamoto, Yoshiaki; Iijima, Kazuki

Journal of Environmental Radioactivity, 146, p.125 - 133, 2015/08

https://doi.org/10.1016/j.jenvrad.2015.04.013

Radiocaesium activity concentrations (Cs, Cs) were measured in parmelioid lichens collected within the Fukushima Prefecture approximately 2 y after the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident. A total of 44 samples consisting of nine species were collected at 16 points within a 60 km radius of the FDNPP. The activity concentration of Cs ranged from 4.6 to 1000 kBq kg and for Cs ranged from 7.6 to 1740 kBq kg. A significant positive correlation was found between the Cs activity concentration in lichens and the Cs deposition density on soil, based on the calculated Spearman's rank correlation coefficients as = 0.90 ( 0.01). The two dominant species, Flavoparmelia caperata and Parmotrema clavuliferum, showed strong positive correlations, for which the r values were calculated as 0.92 ( 0.01) and 0.90 ( 0.01) respectively. Therefore, they are suggested as biomonitoring species for levels of radiocaesium fallout within the Fukushima Prefecture.

Comparison of Ne and Ar seeded radiative divertor plasmas in JT-60U

Nakano, Tomohide; JT-60 Team

Journal of Nuclear Materials, 463, p.555 - 560, 2015/08

https://doi.org/10.1016/j.jnucmat.2014.11.127

In H-mode plasmas with Ne, Ar and a mixture of Ne and Ar injection, the divertor radiation power fraction amongst these impurities in addition to an intrinsic impurity, C, is investigated. In plasmas with the inner divertor plasma attached, carbon is the biggest radiator, whichever impurites, Ne, Ar or a mixture of Ar and Ne is injected. In contrast, in plasmas with the inner divertor plasma detached, Ne is the biggest radiator due to a significantly high recombination radiation from Ne VIII. Ar is always a minor contributor in plasmas with the innder divertor both attached and detached.

Decontamination and volume reduction of cesium-contaminated soil by combining soil solidification with interpolyelectrolyte complex and wet classification

Yamashita, Yuji*; Yanase, Nobuyuki; Nagano, Tetsushi; Mitamura, Hisayoshi; Naganawa, Hirochika

Journal of Radioanalytical and Nuclear Chemistry, 305(2), p.583 - 587, 2015/08

https://doi.org/10.1007/s10967-015-4016-6

We propose a method for the decontamination and waste volume reduction of cesium-contaminated soil. The soils were solidified with an interpolyelectrolyte complex solution and classified into several size fractions by wet sieving. -ray spectrometry of these fractions showed that the distribution ratio of the activity concentration of coarse soil particles decreased, whereas that of soil particles under 0.075 mm increased relative to reference samples. Results show that the fine soil particles, on which radioactive cesium accumulates, were removed from the surface of the coarse soil particles during, and remained in the washing water.

Experiments of coolant accumulation in SG U tube and analytical model development

Yamaji, Tatsuya*; Koizumi, Yasuo; Yamazaki, Kohei*; Otake, Hiroyasu*; Hasegawa, Koji*; Onuki, Akira*; Kanamori, Daisuke*

Konsoryu Shimpojiumu 2015 Koen Rombunshu (USB Flash Drive), 2 Pages, 2015/08

Experiments of condensing counter-current two-phase flow in a vertical pipe were performed. This study was intended to examine water accumulation in the up-flow side of steam generator U-tubes of a PWR during the reflux cooling stage of a small break LOCA. It has been apprehended that the water accumulation may result in temporary core liquid level depression. The inner diameter and the length of a test flow channel used in the experiments were 18 mm and 4 m, respectively. The experiments were performed by using steam and water at 0.1 MPa. Two kinds of experiments were conducted; visualization experiments by using a transparent test section and quantitative water accumulation evaluation experiments by using a brass test section. Even if water on the inner surface of the test pipe could not flow downward at the lower portion of the test pipe, a part of water became to flow downward at the upper portion of the test pipe since steam velocity decreased because of condensation. Thus, two-phase mixture level was formed in the upper portion of the test pipe, which resulted in the water accumulation in the pipe. The model to predict the water accumulation was proposed. It predicted the water accumulation reasonably well.