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Journal Articles

Hot cell equipment improvement effortsat Analytical Laboratory in Tokai Reprocessing Plant

Ishibashi, Atsushi; Masui, Kenji; Goto, Yuichi; Yamamoto, Masahiko; Taguchi, Shigeo; Ishikawa, Satoshi*; Ishikawa, Tomoya*

Nihon Hozen Gakkai Dai-19-Kai Gakujutsu Koenkai Yoshishu, p.18 - 21, 2023/08

An inner-box typed hot cell for analysis of highly radioactive samples has been operated for about 40 years in Tokai Reprocessing Plant since its installation in 1980. During the operation of analytical hot cell, improvement and upgrades including auxiliary equipment have been performed, in addition to keep the equipment in proper condition through periodic inspections and maintenance. This paper describes about these efforts for analytical hot cell and its results.

Journal Articles

Development of a local exhaust device for removal of radioactive waste from glove-box for handling nuclear fuel materials

Ishibashi, Atsushi; Saegusa, Yu; Aoya, Juri; Yamamoto, Masahiko; Taguchi, Shigeo; Kuno, Takehiko

Nihon Hozen Gakkai Dai-18-Kai Gakujutsu Koenkai Yoshishu, p.241 - 244, 2022/07

no abstracts in English

Journal Articles

Transition of near surface resistivity of tunnel wall during drift closure test

Ozaki, Yusuke; Ishibashi, Masayuki; Matsushita, Tomoaki*; Masumoto, Kazuhiko*; Imasato, Takehiko*

Proceedings of 13th SEGJ International Symposium (USB Flash Drive), 4 Pages, 2018/11

In the Mizunami Underground Research Laboratory, Groundwater REcoverty Experiment in Tunnel (GREET) is performed to understanding the recovery process of geological environment after the closure of drift. In this experiment, we performed 2D electrical resistivity surveys three times. First survey was performed before the closure of test drift. Second and third surveys were performed after the closure test. The first survey detected two layers conformation that consists of conductive and resistive zones at shallower and deeper part from the drift surface, respectively. These layers correspond to the shotcrete and host rock, respectively. Second and third measurements show that the conductive zone expanded to deeper resistive part while the shallower conductive part did not change. We concluded that we captured the saturation process of dried fractures near the drift wall by closure of drift as an electrical resistivity response.

JAEA Reports

Report on analytical activities in potentially hazardous materials mitigation measures at the Plutonium Conversion Development Facility; 2015.12 $$sim$$ 2016.10

Horigome, Kazushi; Taguchi, Shigeo; Ishibashi, Atsushi; Inada, Satoshi; Kuno, Takehiko; Surugaya, Naoki

JAEA-Technology 2017-008, 14 Pages, 2017/05

JAEA-Technology-2017-008.pdf:1.15MB

The plutonium solution had been converted into MOX powder to mitigate the potential hazards of storage plutonium solution such as hydrogen generation at the Plutonium Conversion Development Facility. The plutonium conversion operations had been started in April, 2014, and had been finished in July, 2016. With respect to the samples taken from the conversion process, about 2,200 items of plutonium/uranium solutions and MOX powders had been analyzed for the operation control in the related analytical laboratories at the Tokai Reprocessing Plant. This paper describes the reports on analytical activities and related maintenance works in the analytical laboratories conducted from December, 2015 to October, 2016.

JAEA Reports

Report on analytical activities in potentially hazardous materials mitigation measures at the Plutonium Conversion Development Facility; 2014.4 $$sim$$ 2015.12

Horigome, Kazushi; Suzuki, Hisanori; Suzuki, Yoshimasa; Ishibashi, Atsushi; Taguchi, Shigeo; Inada, Satoshi; Kuno, Takehiko; Surugaya, Naoki

JAEA-Technology 2016-026, 21 Pages, 2016/12

JAEA-Technology-2016-026.pdf:1.14MB

In order to mitigate potential hazards of storage plutonium in solution such as hydrogen generation, conversion of plutonium solution into MOX powder has been carried out since 2014 in the Plutonium Conversion Development Facility. With respect to the samples taken from the conversion process, about 3500 items of plutonium/uranium solutions and MOX powders have been analyzed for the operation control in the related analytical laboratories at the Tokai Reprocessing Plant. This paper describes the reports on analytical activities and related maintenance works in the analytical laboratories conducted from April 2014 to December 2015.

Journal Articles

Maintenance experiences at analytical laboratory at the Tokai Reprocessing Plant

Suzuki, Hisanori; Nagayama, Tetsuya; Horigome, Kazushi; Ishibashi, Atsushi; Kitao, Takahiko; Surugaya, Naoki

Nihon Hozen Gakkai Dai-11-Kai Gakujutsu Koenkai Yoshishu, p.214 - 219, 2014/07

The Tokai Reprocessing Plant (TRP) is developing the technology to recover uranium and plutonium from spent nuclear fuel. There is an analytical laboratory which was built in 1978, as one of the most important facilities for process and material control analyses at the TRP. Samples taken from each process are analyzed by various analytical methods using hot cells, glove boxes and hume-hoods. A large number of maintenance work have been so far done and different types of experience have been accumulated. This paper describes our achievements in the maintenance activities at the analytical laboratory at the TRP.

Journal Articles

Discrete fracture network modeling based on in-situ data at underground gallery, 1

Ishibashi, Masayuki; Onoe, Hironori; Sawada, Atsushi; Atsumi, Hiroyuki*; Masumoto, Kazuhiko*; Hosoya, Shinichi*

Dai-42-Kai Gamban Rikigaku Ni Kansuru Shimpojiumu Koenshu (CD-ROM), p.101 - 106, 2014/01

Japan Atomic Energy Agency is proceeding with the Mizunami Underground Research Laboratory Project in order to establish comprehensive techniques for the investigation, analysis and assessment of the deep geological environment in fractured crystalline rock for geological disposal of high level radioactive wastes. We have carried out discrete fracture network modeling, groundwater flow and particle tracking simulation in order to understand the important factors for the solute transport characterizations. In this paper, a method of discrete fracture network modeling based on in-situ data at underground gallery and the influences of different data interpretation are described.

Journal Articles

Discrete fracture network modeling based on in-situ data at underground gallery, 2

Nakajima, Makoto*; Seno, Shoji*; Onoe, Hironori; Ishibashi, Masayuki; Saegusa, Hiromitsu; Sawada, Atsushi

Dai-42-Kai Gamban Rikigaku Ni Kansuru Shimpojiumu Koenshu (CD-ROM), p.107 - 112, 2014/01

Japan Atomic Energy Agency is proceeding with the Mizunami Underground Research Laboratory Project in order to establish comprehensive techniques for the investigation, analysis and assessment of the deep geological environment in fractured crystalline rock for geological disposal of high level radioactive wastes. We have carried out discrete fracture network modeling, groundwater flow and particle tracking simulation in order to understand the important factors for the solute transport characterizations. In this paper, a method for estimating hydraulic parameter of discrete fracture network model based on in-situ data at underground gallery are described.

Journal Articles

Mass production of Nb$$_{3}$$Sn conductors for ITER toroidal field coils in Japan

Takahashi, Yoshikazu; Isono, Takaaki; Hamada, Kazuya; Nunoya, Yoshihiko; Nabara, Yoshihiro; Matsui, Kunihiro; Hemmi, Tsutomu; Kawano, Katsumi; Koizumi, Norikiyo; Oshikiri, Masayuki; et al.

IEEE Transactions on Applied Superconductivity, 22(3), p.4801904_1 - 4801904_4, 2012/06

 Times Cited Count:7 Percentile:41.54(Engineering, Electrical & Electronic)

Japan Atomic Energy Agency is the first to start the mass production of the TF conductors in Phase IV in March 2010 among the 6 parties who are procuring TF conductors in the ITER project. The conductor is cable-in-conduit conductor with a central spiral. A total of 900 Nb$$_{3}$$Sn strands and 522 copper strands are cabled around the central spiral and then wrapped with stainless steel tape whose thickness is 0.1 mm. Approximately 60 tons of Nb$$_{3}$$Sn strands were manufactured by the two suppliers in December 2010. This amount corresponds to approximately 55% of the total contribution from Japan. Approximately 30% of the total contribution from Japan was completed as of February 2011. JAEA is manufacturing one conductor per month under a contract with two Japanese companies for strands, one company for cabling and one company for jacketing. This paper summarizes the technical developments including a high-level quality assurance. This progress is a significant step in the construction of the ITER machine.

Journal Articles

XUV-FEL spectroscopy; He two-photon ionization cross-sections

Sato, Takahiro*; Iwasaki, Atsushi*; Ishibashi, Kazuki*; Okino, Tomoya*; Yamanouchi, Kaoru*; Adachi, Junichi*; Yagishita, Akira*; Yazawa, Hiroki*; Kannari, Fumihiko*; Aoyama, Makoto; et al.

Europhysics News, 42(5), P. 10, 2011/09

The resonant and non-resonant two-photon single ionization processes of He were investigated using intense free electron laser light in the extreme ultraviolet (XUV) region (53.4-61.4 nm) covering the 1s-2p and 1s-3p resonant transitions of He. On the basis of the dependences of the yield of He$$^{+}$$ on the XUV light-field intensity at 53.4, 58.4, 56.0 and 61.4 nm, the absolute values of the two-photon ionization cross sections of He at the four different wavelengths and their dependence on the light-field intensity were determined for the first time.

Journal Articles

Determination of the absolute two-photon ionization cross section of He by an XUV free electron laser

Sato, Takahiro*; Iwasaki, Atsushi*; Ishibashi, Kazuki*; Okino, Tomoya*; Yamanouchi, Kaoru*; Adachi, Junichi*; Yagishita, Akira*; Yazawa, Hiroki*; Kannari, Fumihiko*; Aoyama, Makoto; et al.

Journal of Physics B; Atomic, Molecular and Optical Physics, 44(16), p.161001_1 - 161001_5, 2011/08

 Times Cited Count:35 Percentile:82.97(Optics)

The resonant and non-resonant two-photon single ionization processes of He were investigated using intense free electron laser light in the extreme ultraviolet (XUV) region (53.4-61.4 nm) covering the 1s-2p and 1s-3p resonant transitions of He. On the basis of the dependences of the yield of He$$^{+}$$ on the XUV light-field intensity at 53.4, 58.4, 56.0 and 61.4 nm, the absolute values of the two-photon ionization cross sections of He at the four different wavelengths and their dependence on the light-field intensity were determined for the first time.

JAEA Reports

Precise and accurate determination of plutonium by controlled-potential coulometry and its uncertainty evaluation

Yamamoto, Masahiko; Ishibashi, Atsushi; Nagayama, Tetsuya; Surugaya, Naoki; Kurosawa, Akira; Hiyama, Toshiaki

JAEA-Technology 2010-040, 28 Pages, 2010/12

JAEA-Technology-2010-040.pdf:0.97MB

Precise analysis of plutonium is necessary for material control and safeguards in nuclear facility. Thus, controlled-potential coulometry, which yields absolute results and high precision, was applied for the determination of plutonium. The coulometry system and sample pretreatment procedures were optimized following ISO12183:2005. Plutonium sample prepared from NBL CRM-126 Pu metal was measured and agreed well with certified value. For spike preparation of isotope dilution mass spectrometry (IDMS), plutonium solution was prepared from MOX powder. Plutonium content was 15.5995 mgPu/g. The uncertainty was calculated by ISO/BIPM Guide to the Expression of Uncertainties in Measurements. The relative expanded uncertainty was 0.023% with confidence interval of 95%. The results were in good agreement with those obtained by IDMS. Thus the proposed coulometry method was successfully applied for the determination of plutonium at the highest level of precision and accuracy.

Journal Articles

Development of a TES microcalorimeter for spectroscopic measurement of LX-rays emitted by transuranium elements

Maehata, Keisuke*; Nakamura, Keisuke*; Yasumune, Takashi*; Ishibashi, Kenji*; Takasaki, Koji; Tanaka, Keiichi*; Odawara, Akikazu*; Nagata, Atsushi*

Journal of Nuclear Science and Technology, 47(3), p.308 - 313, 2010/03

 Times Cited Count:5 Percentile:35.91(Nuclear Science & Technology)

A phase transition edge sensor (TES) microcalorimeter was developed for the energy dispersive measurement of LX-ray photons emitted from transuranium elements. The phase transition temperature of the TES was designed to be 200 mK by using bilayer structure of Au of 120 nm thick and Ti of 50 nm thick. The Au layer of 5.0 $$mu$$m thick was deposited on the Au/Ti bilayer for absorption efficiency of 50% and counting rate of 100 counts per second in the detection of LX-ray photons with the energy from 10 to 20 keV. The TES microcalorimeter was operated for the detection of LX-ray photons emitted from $$^{241}$$Am, $$^{238}$$Pu and $$^{239}$$Pu sources. The decay time constant of 180 $$mu$$s of detection signal pulses allowed the TES microcalorimeter operating with the counting rate higher than 100 counts per second. The energy resolution was obtained to be 50 eV of FWHM value for a peak corresponding to $$^{237}$$Np L$$beta$$$$_{1}$$ X-ray of 17.75 keV.

JAEA Reports

Development of production technology of ZrC-coated particle, 2 (Contract research)

Yasuda, Atsushi; Ueta, Shohei; Aihara, Jun; Ishibashi, Hideharu*; Sawa, Kazuhiro

JAEA-Technology 2008-083, 11 Pages, 2009/01

JAEA-Technology-2008-083.pdf:3.14MB

The Very-High-Temperature Reactor (VHTR) is one of the candidates for the Generation IV nuclear energy system. ZrC coated fuel particles are expected to make the performance of the VHTR higher. Therefore, we are investigating the ZrC-coating process. From April 2007 to March 2008, ZrC-outer pyrolytic carbon (OPyC) layer continuous coating tests were carried out with the nonnuclear particles and we succeeded to coat continuously the ZrC layer and the OPyC layer with the thicknesses up to about 27 and about 48 $$mu$$m, respectively, in the batch scale of 100 g.

Journal Articles

TEM/STEM observation of ZrC coating layer for advanced high-temperature gas-cooled reactor fuel, Part II

Aihara, Jun; Ueta, Shohei; Yasuda, Atsushi; Ishibashi, Hideharu; Mozumi, Yasuhiro; Sawa, Kazuhiro; Motohashi, Yoshinobu*

Journal of the American Ceramic Society, 92(1), p.197 - 203, 2009/01

 Times Cited Count:7 Percentile:42.55(Materials Science, Ceramics)

The ZrC coating layer was fabricated with bromide process at JAEA. In a later stage of the project, we have successfully kept nominal deposition temperature almost constant. Microstructures of the ZrC layers, of which nominal deposition temperatures were able to measure, were characterized by means of TEM and STEM and the results were compared and discussed with those obtained for different batches including those reported in a previous study. The ZrC grains were oriented in the ZrC layers deposited at about 1630 K. This feature was rather different from that reported in the previous study. The formation of fairly different PyC structures was found on the PyC/ZrC boundary as well as around the pores existing near the boundary. Fibrous carbons were observed on the PyC/ZrC boundary produced in a batch deposited at a higher temperature (nominal temperature was 1769 K); no such fibrous carbons were found in a batch deposited at a lower temperature (nominal temperature was 1632 K).

Journal Articles

Active core structure of terfestatin A, a new specific inhibitor of auxin signaling

Hayashi, Kenichiro*; Yamazoe, Atsushi*; Ishibashi, Yuki*; Kusaka, Naoyuki*; Ono, Yutaka; Nozaki, Hiroshi*

Bioorganic & Medicinal Chemistry, 16(9), p.5331 - 5344, 2008/05

 Times Cited Count:20 Percentile:52.12(Biochemistry & Molecular Biology)

The auxins, plant hormones, regulate many aspects of the growth and development of plants. Terfestatin A (TrfA), a novel auxin signaling inhibitor, was identified in a screen of ${it Streptomyces sp}$. F40 extracts for inhibition of the expression of an auxin-inducible gene. However, the mode of action of TrfA has not been elucidated. To identify the active core structure, 25 derivatives of TrfA were synthesized and their inhibitory activities against auxin-inducible gene expression were evaluated. The structure-activity relationships revealed the essential active core structure of TrfA, 3-butoxy-4-methylbiphenyl-2,6-diol, which will lead to the design of biotin-tagged active TrfA.

Journal Articles

Fabrication of uniform ZrC coating layer for the coated fuel particle of the very high temperature reactor

Ueta, Shohei; Aihara, Jun; Yasuda, Atsushi; Ishibashi, Hideharu; Takayama, Tomoo; Sawa, Kazuhiro

Journal of Nuclear Materials, 376(2), p.146 - 151, 2008/05

 Times Cited Count:56 Percentile:95.75(Materials Science, Multidisciplinary)

The Very-High-Temperature Reactor (VHTR) is the one of the most promising candidates for the Generation IV Nuclear Energy System. The VHTR fuel should exhibit excellent safety performance up to burn-ups of about 15 to 20%FIMA and fluences of 6$$times$$10$$^{25}$$ n/m$$^{2}$$(E$$>$$0.1 MeV). There is no experimental data which has proved the intactness of conventional SiC-coated fuel particles under such severe condition. Japan Atomic Energy Agency (JAEA) developed Zirconium carbide (ZrC)-coated fuel particles which is expected to maintain its intactness under higher temperature and burn-up compared with SiC-coating layer. JAEA has newly started the development of coating process by large-scale and of inspection method, and the irradiation of ZrC-coated particles from 2004. The fabrication tests of ZrC-coating have been started by new-series coater, and uniform ZrC coating layer has successfully been fabricated by the improvement of temperature control technique.

Journal Articles

Development on fabrication and inspection techniques for the ZrC-coated fuel particle as an advanced high temperature gas cooled reactor fuel

Ueta, Shohei; Aihara, Jun; Yasuda, Atsushi; Ishibashi, Hideharu; Mozumi, Yasuhiro; Sawa, Kazuhiro; Minato, Kazuo

Hyomen, 46(4), p.222 - 232, 2008/04

Japan Atomic Energy Agency (JAEA) is developing the zirconium carbide (ZrC) coated fuel particle which has better refractoriness and chemical stability than the conventional silicon carbide (SiC) coated fuel particle. In the present study, ZrC coating tests were carried out by the enlarged 200 g-scale ZrC coater comparing with the previous study. Finally, the stoichiometric ZrC layer was successfully fabricated by obtaining relationships between properties of ZrC, coating temperature and batch size through coating tests. In addition, not only inspection methods for coating thickness and density, but also treatment technique to remove pyrocarbon (PyC) layer were developed in order to evaluate the quality of the ZrC coated fuel particle. Present R&D will contribute to the practicability of the ZrC coated fuel particle as a fuel for the advanced high temperature gas cooled reactor such as the Very High Temperature Reactor (VHTR).

Journal Articles

TEM/STEM observation of ZrC-coating layer for advanced high-temperature gas-cooled reactor fuel

Aihara, Jun; Ueta, Shohei; Yasuda, Atsushi; Ishibashi, Hideharu; Takayama, Tomoo; Sawa, Kazuhiro; Motohashi, Yoshinobu*

Journal of the American Ceramic Society, 90(12), p.3968 - 3972, 2007/12

Japan Atomic Energy Agency (JAEA) has started to study and develop ZrC coated fuel particles for advanced high temperature gas cooled reactors. This paper mainly focuses on the microstructures of the ZrC and isotropic dense pyrolytic carbon (PyC) coating layer produced in the early stage of the project. The structure of free carbon region in the ZrC coating layer appears to be such that c-plane was along with the ZrC grain boundary. It appears that the existence of the free carbon phase, especially with such structure, deteriorates the fission product (FP) retention performance in addition to the mechanical strength of ZrC. The PyC coating layer appears to be a medium-range ordered amorphous structure.

JAEA Reports

Investigation on inspection methods for ZrC-coated fuel particle; Applicability evaluation of inspection methods for SiC-coated fuel particle

Takayama, Tomoo*; Ueta, Shohei; Aihara, Jun; Yasuda, Atsushi*; Ishibashi, Hideharu*; Sawa, Kazuhiro

JAEA-Research 2007-061, 32 Pages, 2007/09

JAEA-Research-2007-061.pdf:15.93MB

As the conventional SiC coated fuel particle, the ZrC coated fuel particle is proposed as a fuel for the Very High Temperature Gas-cooled Reactor (VHTR) which is one of Generation IV nuclear reactors. Applicability of inspection methods of SiC-coated fuel particle for ZrC-coated fuel particle has been examined by comparing properties of ZrC with SiC. It was suggested that hardness, absorption X-ray coefficient, density, oxidation-resistant and chemical stability of SiC were dominant properties for conventional inspection methods such as SiC coating layer thicknesses, coating layers densities for both SiC and O-PyC layers, thorough-coatings failure fraction and SiC coating layer failure fraction. With regards to the applicability of the inspection for the SiC-coated particle, some difficulties are revealed on coating layers densities for both ZrC and O-PyC layers and of ZrC failure fraction, and it was suggested that they were major issues to be solved.

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