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Mo/
Tc generator by (n,
) methodFujita, Yoshitaka; Seki, Misaki; Namekawa, Yoji*; Nishikata, Kaori; Kimura, Akihiro; Shibata, Akira; Sayato, Natsuki; Tsuchiya, Kunihiko; Sano, Tadafumi*; Fujihara, Yasuyuki*; et al.
KURNS Progress Report 2018, P. 155, 2019/08
no abstracts in English
pellets for Mo-99 productionFujita, Yoshitaka; Nishikata, Kaori; Namekawa, Yoji*; Kimura, Akihiro; Shibata, Akira; Sayato, Natsuki; Tsuchiya, Kunihiko; Sano, Tadafumi*; Fujihara, Yasuyuki*; Zhang, J.*
KURRI Progress Report 2017, P. 126, 2018/08
no abstracts in English
Shudo, Yasuyuki*; Izumi, Atsushi*; Hagita, Katsumi*; Yamada, Takeshi*; Shibata, Kaoru; Shibayama, Mitsuhiro*
Macromolecules, 51(16), p.6334 - 6343, 2018/08
Times Cited Count：11 Percentile：39.85(Polymer Science)Hayashi, Hirokazu; Sato, Takumi; Shibata, Hiroki; Tsubata, Yasuhiro
NEA/NSC/R(2017)3, p.427 - 432, 2017/11
Transmutation of long-lived radioactive nuclides including minor actinides (MA: Np, Am, Cm) has been studied in Japan Atomic Energy Agency (JAEA). Pb-Bi cooled sub-critical accelerator-driven system (ADS) is regarded as one of the powerful tools for transmutation of MA under the double strata fuel cycle concept. Uranium-free MA-Pu nitride fuel was chosen as the first candidate for MA transmutation. Reprocessing of spent ADS fuel and reusing MA recovered from the spent ADS fuels is necessary to improve the transmutation ratio. A pyrochemical process has been proposed as the first candidate for reprocessing of the spent nitride fuel for MA transmutation, because this technique has some advantages over aqueous process, such as the resistance to radiation damage, which is an important issue for the fuels containing large amounts of highly radioactive MA, and feasibility for recovering expensive N-15 in the spent fuels to be reused. This paper overviews the current status of the technology development, including our recent study. Development of the anode suitable for electro-refining of nitride fuels and that of the apparatus for renitridation of the metals recovered in Cd cathode for 100g-Cd scale cold tests are main topics. Evaluation of the batch sizes of each process, which is necessary for estimating the scale of the engineering-apparatus, with considering the decay heat of MA and FP, will also be introduced.
pellets for Mo-99 production, 3Ishida, Takuya; Suzuki, Yoshitaka; Nishikata, Kaori; Yonekawa, Minoru; Kato, Yoshiaki; Shibata, Akira; Kimura, Akihiro; Matsui, Yoshinori; Tsuchiya, Kunihiko; Sano, Tadafumi*; et al.
KURRI Progress Report 2015, P. 64, 2016/08
no abstracts in English
Suzuki, Hideya; Tsubata, Yasuhiro; Kurosawa, Tatsuya; Shibata, Mitsunobu; Kawasaki, Tomohiro; Urabe, Shunichi*; Matsumura, Tatsuro
Analytical Sciences, 32(4), p.477 - 479, 2016/04
Times Cited Count：24 Percentile：67.95(Chemistry, Analytical)An impeccable, high-performance new reagent called alkyl diamide amine (ADAAM) was examined from the viewpoint of mutual separation of Am(III) and Eu(III). ADAAM has three donor atoms, one soft N-donor atom and two hard O-donor atoms, in the central frame. The combination of soft and hard atoms affords a tridentate donor set of atoms that ensures remarkable extractability and selectivity of Am(III) and Eu(III) in highly acidic media.
Mo/
Tc production by neutron activation methodIshida, Takuya; Shiina, Takayuki*; Ota, Akio*; Kimura, Akihiro; Nishikata, Kaori; Shibata, Akira; Tanase, Masakazu*; Kobayashi, Masaaki*; Sano, Tadafumi*; Fujihara, Yasuyuki*; et al.
JAEA-Technology 2015-030, 42 Pages, 2015/11
JAEA-Technology-2015-030.pdf:4.82MB
The research and development (R&D) on the production of Mo/Tc by neutron activation method ((n, ) method) using JMTR has been carried out in the Neutron Irradiation and Testing Reactor Center. The specific radioactivity of Mo by (n, ) method is extremely low compared with that by fission method ((n,f) method), and as a result, the radioactive concentration of the obtained Tc solution is also lowered. To solve the problem, we propose the solvent extraction with methyl ethyl ketone (MEK) for recovery of Tc from Mo produced by (n, ) method. We have developed the Mo/Tc separation/extraction/concentration devices and have carried out the performance tests for recovery of Tc from Mo produced by (n, ) method. In this paper, in order to establish an experimental system for Mo/Tc production, the R&D results of the system are summarized on the improvement of the devices for high-recovery rate of Tc, on the dissolution of the pellets, which is the high-density molybdenum trioxide (MoO) pellets irradiated in Kyoto University Research Reactor (KUR), on the production of Tc, and on the inspection of the recovered Tc solutions.
Takeuchi, Tomoaki; Yamamoto, Keiichi; Otsuka, Noriaki; Shibata, Hiroshi; Shibata, Akira; Takemoto, Noriyuki; Tsuchiya, Kunihiko; Sano, Tadafumi*; Unesaki, Hironobu*; Fujihara, Yasuyuki*; et al.
KURRI Progress Report 2014, P. 108, 2015/07
Investigation of a relation between output power and brightness of Cherenkov light of a specific fuel element at KUR by a CCD camera was performed due to a development of a real-time in-core measurement technique using Cherenkov light. The results indicate that the inhomogeneous distribution of output power and the shadow of the control-rod guide tubes and the other irradiation equipment have significant effects on the brightness of the Cherenkov light. These effects could be suppressed by using a number of cameras located at various positions.
Otsuka, Noriaki; Takeuchi, Tomoaki; Yamamoto, Keiichi; Shibata, Akira; Kimura, Nobuaki; Takemoto, Noriyuki; Tanimoto, Masataka; Tsuchiya, Kunihiko; Sano, Tadafumi*; Unesaki, Hironobu*; et al.
KURRI Progress Report 2013, P. 215, 2014/10
Investigation of a relation between reactor power and brightness of Cherenkov light at Kyoto University Research reactor (KUR) by a CCD camera was performed due to a development of a real-time in-core measurement technique using Cherenkov light. Analyzing the brightness value of individual RGB color component at each pixel, some of the G and B brightness values reached the maximum value of 8-bit binary number, i.e. 255, above about 2-3 MW. Therefore, we corrected the G and B brightness values by the R signals whose brightness value did not saturate even at 5 MW, the maximum reactor power of KUR. Then, the total brightness value was in proportion to the reactor power after the correction. These results indicate the reactor power can be estimated by the observation of Cherenkov light.
Kawakami, Sho*; Shibata, Yoshihide; Watanabe, Kiyomasa*; Ono, Noriyasu*; Isayama, Akihiko; Takizuka, Tomonori*; Kawano, Yasunori; Okamoto, Masaaki*
Physics of Plasmas, 20(11), p.112507_1 - 112507_6, 2013/11
Times Cited Count：2 Percentile：8.81(Physics, Fluids & Plasmas)According to an early work on the behavior of the plasma current decay in the JT-60U disruptive discharges caused by the radiative collapse with a massive neon-gas-puff, the increase of the internal inductance mainly determined the current decay time of plasma current during the initial phase of current quench. To investigate what determines the increase of the internal inductance, we focus attention on the relationship between the electron temperature (or the resistivity) profile and the time evolution of the current density profile, and carry out numerical calculations. As a result, we find the reason of the increase of the internal inductance: The current density profile at the start of the current quench is broader than an expected current density profile in the steady state, which is determined by the temperature (or resistivity) profile. The current density profile evolves into peaked one and the internal inductance is increasing.
Kimura, Nobuaki; Takeuchi, Tomoaki; Shibata, Akira; Takemoto, Noriyuki; Kimura, Akihiro; Naka, Michihiro; Nishikata, Kaori; Tanimoto, Masataka; Tsuchiya, Kunihiko; Sano, Tadafumi*; et al.
KURRI Progress Report 2012, P. 209, 2013/10
In research reactors, CCD cameras are used to observe reactor core for reactor operation management, e.g. to prevent debris from falling. In order to measure the reactor power and fuel burnup exactly by means of observation of Cherenkov light, the development of the on-line measurement device started in 2009. In this study, the wavelength and the absolute irradiance of the Cherenkov light were measured by a spectrometer, and the Cherenkov light was observed by the CCD camera. As a result, the measurement value is good agreement with the nominal value. On the other hand, the value by the visible imaging system was obtained the same tendency of nominal transmittance value of ND-filters.
Endo, Kiyoshi*; Shibata, Yasushi*; Yamamoto, Tetsuya*; Nakai, Kei*; Matsumura, Akira*; Sato, Takahiro; Yokoyama, Akihito; Koka, Masashi; Okubo, Takeru; Yamazaki, Akiyoshi; et al.
JAEA-Review 2011-043, JAEA Takasaki Annual Report 2010, P. 86, 2012/01
Watanabe, So; Senzaki, Tatsuya; Shibata, Atsuhiro; Nomura, Kazunori; Koma, Yoshikazu; Nakajima, Yasuo
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 6 Pages, 2011/12
Extraction chromatography experiments with two promising flow-sheets on genuine high level liquid wastes were carried out for demonstrating the feasibility of the method. One flow-sheet consists of CMPO/SiO
-P and HDEHP/SiO-P adsorbent columns, and the other consists of TODGA/ SiO-P and isoHex-BTP/SiO-P adsorbent columns. Although recovery yields of MA and decontamination factors of FPs obtained by those experiments were lower than the required values, the second flow-sheet is expected to achieve the required performance providing that some minor improvements on the flow-sheet or the adsorbents are applied.
Shibata, Yoshihide*; Watanabe, Kiyomasa*; Ono, Noriyasu*; Okamoto, Masaaki*; Isayama, Akihiko; Kurihara, Kenichi; Oyama, Naoyuki; Nakano, Tomohide; Kawano, Yasunori; Matsunaga, Go; et al.
Plasma and Fusion Research (Internet), 6, p.1302136_1 - 1302136_4, 2011/10
no abstracts in English
Shibuta, Yasushi*; Unoura, Seiji*; Sato, Takumi; Shibata, Hiroki; Kurata, Masaki*; Suzuki, Toshio*
Journal of Nuclear Materials, 414(2), p.114 - 119, 2011/07
Times Cited Count：16 Percentile：75.56(Materials Science, Multidisciplinary)The uranium dendrite growth on cathode during pyroprocessing of uranium is investigated using a novel phase-field model, in which electrodeposition of uranium and zirconium from molten-salt is taken into account. The threshold concentration of zirconium in molten salt demarcating the dendritic and planar growth is then estimated as a function of the current density. Moreover, growth process of both the dendritic and planar electrodeposits has been demonstrated by way of varying the mobility of the phase field, which consists of the effect of attachment kinetics and diffusion.
Shibata, Yoshihide*; Watanabe, Kiyomasa*; Okamoto, Masaaki*; Ono, Noriyasu*; Isayama, Akihiko; Kurihara, Kenichi; Nakano, Tomohide; Oyama, Naoyuki; Kawano, Yasunori; Matsunaga, Go; et al.
Nuclear Fusion, 50(2), p.025015_1 - 025015_7, 2010/01
Times Cited Count：17 Percentile：54.34(Physics, Fluids & Plasmas)no abstracts in English
Oda, Yasuhisa; Shibata, Teppei*; Komurasaki, Kimiya*; Takahashi, Koji; Kasugai, Atsushi; Sakamoto, Keishi
Journal of Propulsion and Power, 25(1), p.118 - 122, 2009/01
Times Cited Count：24 Percentile：82.53(Engineering, Aerospace)Muramatsu, Yasuyuki; Okawara, Masami; Suzuki, Toshiyuki; Shibata, Isao; Fuketa, Toyoshi
JAEA-Technology 2007-028, 47 Pages, 2007/03
JAEA-Technology-2007-028.pdf:4.76MB
As a part of Advanced LWR Fuel Performance and Safety Research Program, irradiation experiments are conducted with high burnup uranium dioxide fuel and uranium-plutonium mixed oxide (MOX) fuel in the Nuclear Safety Research Reactor. When an irradiation capsule is transferred and loaded to the reactor core, a capsule loader is used. The previous capsule loader, however, could not have enough shielding capability against neutron flux from high burnup MOX fuel. In order to fulfill the requirement and to handle a new high pressure water capsule, accordingly, a type-B capsule loader was developed.
Murao, Hiroyuki; Muramatsu, Yasuyuki; Okawara, Masami; Shibata, Isao
JAEA-Technology 2006-062, 32 Pages, 2007/02
JAEA-Technology-2006-062.pdf:1.81MB
In NSRR (Nuclear Safety Research Reactor) experiments, test fuels are inserted in the especial capsule and the capsule will be inserted into the experimental tube which is located in the center of reactor core. In NSRR, there are 17 types of atmospheric pressure capsule, and one of them Type X-IV atmospheric pressure capsule has been produced 6 times under authorization of Ministry of Education, Culture, Sports, Science and Technology (MEXT). Application for the 7th time of authorization was submitted to the MEXT in June 2006. On this application, standard which is used to design was changed to The Japan Society of Mechanical Engineers (JSME) S NC1-2005 from the Notification 501 of the Ministry of Economy, Trade and Industry (METI). The JSME S NC1-2005 introduced the service condition in addition to the reactor condition which has been used in the Notification 501. In this application, stress limits were calculated based on the service condition. The JSME S NC1-2005 requires estimation of combined stress for Class1 support structures, which was unnecessary in the Notification 501. In this application, combined stresses were calculated and confirmed not to exceed the stress limits.
Oda, Yasuhisa*; Shibata, Teppei*; Komurasaki, Kimiya*; Takahashi, Koji; Kasugai, Atsushi; Sakamoto, Keishi
Journal of Space Technology and Science, 22(2), p.30 - 37, 2006/00
A thrust generation model for microwave rocket was studied. The model was based on shock wave propagation driven by atmospheric plasma as analogy of pulse detonation engine (PDE). Pressure histories in the thruster were measured using pressure gauges and compared to the model. The shock wave was measured from pressure history in the thruster model. The relationship between the shock-wave traveling time and propagation distance showed good linearity. At the same time, the propagation velocity of the ionization front in the tube was also measured. The velocity is also nearly constant during the propagation. The both velocities were increased with the power density. The both the ionization front and the shock wave propagated at the same velocity when they propagated at supersonic speed. Thrust impulse was estimated from pressure history. Estimated thrust showed good agreement to the result of the flight experiment.
