Japan
Seismic response analysis of RAPSODIE core mock-up in-air experiment
Morishita, M. (Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center)
IAEA-TECDOC--829, pp:12-36
Seismic response analysis of FBR core by FINAS code
Morishita, M. (Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center)
IAEA-TECDOC--882, pp:12-36
Fabrication of uranium-plutonium mixed nitride and thermally stable carbide fuels
Arai, Y.; Fukushima, S.; Shiozawa, K.; Handa, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan))
IAEA-TECDOC--466, pp:25-33
Philosophy of leak before break assessment for Japanese prototype FBR
Wakai, T.; Aoto, K.; Ichimiya, M. (Japan Nuclear Cycle Development Institute (JNC), O-arai Engineering Center, Ibaraki (Japan)); Ito, K. (Japan Nuclear Cycle Development Institute (JNC), Monju Construction Office, Ibaraki (Japan))
IAEA-TECDOC--1406, pp:25-33
A review of the fast reactor program in Japan
Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
IAEA-TECDOC--791, pp:28-44
The status of studies on fast reactor core thermal hydraulics at PNC
Nishimura, M.; Ohshima, H.; Kamide, H.; Yamaguchi, K.; Yamaguchi, A. (O-arai Engineering Center, Power Reactor and Nuclear Fuel Development Corporation, O-arai, Ibaraki-ken (Japan))
IAEA-TECDOC--1157, pp:28-45
Operational experience and upgrading program of the experimental fast reactor JOYO
Aoyama, T.; Odo, T.; Suzuki, S.; Yogo, S. (Japan Nuclear Cycle Development Institute (JNC), Ibaraki (Japan))
IAEA-TECDOC--1405, pp:29-61
Partitioning and transmutation research and development program (OMEGA) in Japan
Mukaiyama, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan))
IAEA-TECDOC--693, pp:30-36
Quality control of uranium-plutonium mixed carbide and nitride fuels
Maeda, A.; Iwai, T.; Ohmichi, T.; Handa, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan))
IAEA-TECDOC--466, pp:34-41
Consideration on safety margin in Joyo thermal design
Inoue, T.; Yoshino, F.; Izumi, A. (Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan))
IAEA-TECDOC--166, pp:37-84
RAPSODIE core mock-up seismic analyses by FINDS code
Itoh, K. (Mitsubishi Atomic Power Industries, Yokohama (Japan)); Sato, T.; Aizawa, I. (Nuclear Development Corp., Tokai, Ibaraki (Japan))
IAEA-TECDOC--829, pp:37-78
Seismic response analysis of Rapsodie core mock-up in water experiment
Morishita, M. (Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center)
IAEA-TECDOC--882, pp:37-58
Status of minor actinide transmutation study at CRIEPI
Sasahara, A.; Kurata, M. (Central Research Inst. of Electric Power Industry, Tokyo (Japan))
IAEA-TECDOC--693, pp:37-42
Development of accelerator driven transmutation system concept and
related R&D activities at JAERI
T. Takizuka, T. Osugi, H. Takano
IAEA-TECDOC--1356, pp:37-54
Reactor strategy and advanced fuel technology in Japan: Current status and future plan
Saito, N. (Science and Technology Agency, Tokyo (Japan). Atomic Energy Bureau)
IAEA-TECDOC--577, pp:39-43
Studies on thorium fuel cycle in Japan
Hirakawa, H. (Tohoku University, Sendai (Japan))
IAEA-TECDOC--1319, pp:42-53
Improvements in MOX fuel utilization in Japan and technological developments for an economical FBR fuel cycle
Mishima, T. (Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works)
IAEA-TECDOC--577, pp:44-61
A review of the fast reactor program in Japan
Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
IAEA-TECDOC--741, pp:46-64
Sodium leakage experience at the prototype FBR Monju
Miyakawa, A.; Maeda, H.; Kani, Y.; Ito, K. (Monju Construction Office, Japan Nuclear Cycle Development Institute, Fukui-ken (Japan))
IAEA-TECDOC--1180, pp:49-62
Seismic response analysis of the PEC reactor core mock-up
Morishita, M. (Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center)
IAEA-TECDOC--798, pp:51-76
Verification and validation analyses of LMFBR core mock-up seismic experiments by finds code
Itoh, K. (Mitsubishi Heavy Industries, Yohomama (Japan)); Satoh, T.; Aizawa, I. (Nuclear Development Corp., Tokai, Ibaraki (Japan))
IAEA-TECDOC--882, pp:59-109
The development of demonstration fast breeder reactor (DFBR)
Nakamura, T.; Inagaki, T. (Japan Atomic Power Co., Tokyo (Japan)); Shibata, Y. (Hitachi Ltd, Hitachi (Japan)); Tarutani, K. (Toshiba Corp., Tokyo (Japan)); Okada, K. (Mitsubishi Heavy Industries, Ltd, Yokohama (Japan))
IAEA-TECDOC--907, pp:59-70
Research and development of uranium-plutonium mixed carbide and nitride fuels at JAERI
Suzuki, Y.; Arai, Y.; Handa, M.; Shiba, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept. of Fuels and Materials Research)
IAEA-TECDOC--577, pp:70-79
A simplified crack growth assessment procedure for PCP in FBR
Wakai, T.; Aoto, K. (Japan Nuclear Cycle Development Institute (JNC), O-arai Engineering Center, Ibaraki (Japan))
IAEA-TECDOC--1406, pp:73-85
Partitioning and transmutation R and D program 'OMEGA' and present status of the transmutation
study at JAERI
Mukaiyama, T.; Takizuka, T.; Mizumoto, M.; Yoshida, H. (Japan Atomic Energy
Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)
IAEA-TECDOC--783, pp:75-92
Creep-fatigue evaluation method for type 304 and 316FR SS
Wada, Y.; Aoto, K.; Ueno, F. (Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center)
IAEA-TECDOC--933, pp:75-86
PEC core mock-up seismic analyses by the finds code
Itoh, K. (Mitsubishi Atomic Power Industries, Inc., Tokyo (Japan)); Sato, T.; Aizawa, I. (Nuclear Development Corp., Tokai, Ibaraki (Japan))
IAEA-TECDOC--798, pp:77-96
Seismic analysis for the FBR core mock-up RAPSODIE experiments using the SAFA program
Horiuchi, T.; Motomiya, T. (Hitachi Ltd, Ibaraki (Japan). Mechanical Engineering Lab.)
IAEA-TECDOC--829, pp:79-86
Research and development of HTGR fuel at JAERI
Fukuda, K.; Yamagishi, S.; Ikawa, K.; Shiba, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept. of Fuels and Materials Research)
IAEA-TECDOC--577, pp:80-92
Minor actinide transmutation in fission reactors and fuel cycle considerations
Mukaiyama, T.; Yoshida, H.; Ogawa, T. (Japan Atomic Energy Research Inst., Tokai,
Ibaraki (Japan))
IAEA-TECDOC--693, pp:86-93
Calculation of PEC and RAPSODIE Tests by SALCON code
Kobayashi, T. (Toshiba Corp., Isogo Engineering Center, Yokohama (Japan). Advanced Reactor Dept.)
IAEA-TECDOC--829, pp:87-116
Advanced marine reactor MRX and its application for electricity and heat co-generation
Ishida, T.; Ochiai, M. (Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken (Japan)); Hoshi, T. (Research Organization for Information Science and Technology, Tokai-mura, Naka-gun, Ibaraki-ken (Japan))
IAEA-TECDOC--1172, pp:88-109
Thermomechanical and fracture mechanics analysis on a tee junction of LMFR secondary circuit due to thermal striping phenomena
Kasahara, N. (O-arai Engineering Center (Japan))
IAEA-TECDOC--1318, pp:89-116
Research and development on the partitioning process at JAERI
Morita, Y.; Yamaguchi, I.; Kondo, Y.; Shirahashi, K.; Yamagishi, I.; Fujiwara, T.;
Kubota, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai
Research Establishment)
IAEA-TECDOC--783, pp:93-104
Calculation of the PEC test by the SALCON code
Kobayashi, T. (Toshiba Corp., Yokohama (Japan))
IAEA-TECDOC--798, pp:97-105
Characteristics of TRU transmutation in an LMFBR
Wakabayashi, T.; Yamaoka, M. (Power Reactor and Nuclear Fuel Development Corp.,
Oarai, Ibaraki (Japan). Oarai Engineering Center)
IAEA-TECDOC--693, pp:99-108
Present status of FBR mixed oxide and advanced fuel development at PNC
Endo, H.; Nakajima, I. (Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan))
IAEA-TECDOC--466, pp:102-112
Minor actinide burner reactor and influence of transmutation on fuel cycle facilities
Mukaiyama, T.; Ogawa, T.; Gunji, Y. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)
IAEA-TECDOC--783, pp:105-114
Seismic analysis for PEC fast reactor core experiments using the SAFA program
Horiuchi, T.; Motomiya, T. (Hitachi Ltd., Tokyo (Japan))
IAEA-TECDOC--798, pp:106-117
Evaluation of LMFBR core seismic analysis by the SALCON code
Kobayashi, T. (Toshiba Corp., Yokohama (Japan). Advanced Reactor Dept.)
IAEA-TECDOC--882, pp:110-146
The design of a backup reactor shutdown system of DFBR
Okada, K. (Mitsubishi Heavy Industries, Ltd., Yokohama (Japan)); Tarutani, K. (Toshiba Corp., Tokyo (Japan)); Shibata, Y. (Hitachi Ltd., Tokyo (Japan)); Ueta, M.; Inagaki, T. (Japan Atomic Power Co., Tokyo (Japan))
IAEA-TECDOC--884, pp:111-123
A review of fast reactor programme in Japan
Power Reactor and Fuel Development Corporation (Japan)
IAEA-TECDOC--1015, pp:111-136
Overview of partitioning and transmutation study at PNC
Tani, S.; Ozawa, M.; Wakabayashi, T. (Power Reactor and Nuclear Fuel Devleopment
Corp., Oarai, Ibaraki (Japan))
IAEA-TECDOC--783, pp:115-135
Thorium fuel-cycle development through plutonium incineration by THORIMS-NES (Thorium Molten-Salt nuclear energy synergetics)
Furukawa, K. (Tokai Univ., Kanagawa (Japan). Inst. of Research and Development);
Mitachi, K. (Toyohashi Univ. of Technology, Toyohashi (Japan). Dept. of Energy
Engineering); Lecocq, A. (European Association for Molten-Salt Reactors Development,
Orsay (France)); Furuhashi, A. (Nuclear Material Control Center, Tokyo (Japan));
Chigrinov, S.E. (Radiation Physics and Chemical Problems Inst., Minsk (Belarus))
IAEA-TECDOC--916, pp:115-128
Thermohydraulics computer code system and computational results on thermal striping phenomena at a tee junction of LMFR circuit with the system
Muramatsu, T. (O-arai Engineering Center (Japan))
IAEA-TECDOC--1318, pp:117-144
Thorium cycle implementation through plutonium incineration by thorium molten-salt nuclear energy synergetics
Furukawa, K. (International Thorium Molten-Salt Forum, Oiso (Japan)); Simonenko, V. (Institute of Technical Physics, Snezhinks (Russian Federation)); Mitachi, K. (Toyohashi University of Technology, Toyohashi, Aichi (Japan)); Furuhashi, A. (Nuclear Material Control Center, Tokyo (Japan)); Yoshioka, R. (Toshiba Inc., Yokohama (Japan)); Chigrinov, S. (Radiation Physics and Chemistry Problems Institute, Minsk (Belarus)); Lecocq, A. (EURIWA, Orsay (France)); Kato, Y. (Japan Atomic Energy Research Institute, Tokai (Japan))
IAEA-TECDOC--1319, pp:123-128
Numerical simulations of rubber bearing tests and shaking table tests
Hirata, K.; Matsuda, A.; Yabana, S. (Central Research Institute of Electric Power Industry (Japan))
IAEA-TECDOC--1288, pp:131-165
Design study of He gas-cooled fast breeder reactor
Mochizuki, H.; Izaki, T.; Takitani, K.; Koike, H.; Kobayashi, Y.; Matsuki, Y.; Ooka, T.; Tanaka, R.;
Watanabe, T.; Kobayashi, T. (Kawasaki Heavy Industries Ltd., Tokyo (Japan))
IAEA-TECDOC--154, pp:133-164
Pyrometallurgical partitioning of transuranium elements and the transmutation in metallic fuel FBR
Inoue, T.; Sakata, M.; Kurata, M.; Sakamura, Y.; Hijikata, T.; Kinoshita, K. (Central Research Inst. of Electric Power Industry, Tokyo (Japan))
IAEA-TECDOC--783, pp:137-148
A review of fast reactor program in Japan
Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
IAEA-TECDOC--876, pp:139-169
Conceptual design studies on various types of HLMC fast reactor plants
T. Mihara, Y. Tanaka, Y. Enuma
IAEA-TECDOC--1348, pp:143-150
Analysis of the core seismic experiments using the SAFA program for intercomparison of LMFBR seismic analysis codes
Horiuchi, T. (Hitachi Ltd, Tsuchiura, Ibaraki (Japan). Mechanical Engineering Research Lab.)
IAEA-TECDOC--882, pp:147-174
A simple analytical method to evaluate transient behaviours of metal fueled fast reactors
Ninokata, H.; Hizume, Y.; Sawada, T.; Endo, H. (Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, Tokyo (Japan))
IAEA-TECDOC--1157, pp:150-162
Omega programme in Japan and ADS development at JAERI
T. Mukaiyama (Center for Neutron Science, Japan Atomic Energy Research Institute Tokai-mura, Ibaraki-ken, Japan)
IAEA-TECDOC--1365, pp:153-165
Irradiation behaviour of boron carbide neutron absorber
Kaito, T. (Power Reactor and Nuclear Fuel Development Corp., Oarai Engineering Center, Ibaraki (Japan). Nuclear Fuel Research Section); Maruyama, T.; Onose, S.; Horiuchi, H. (Power Reactor and Nuclear Fuel Development Corp., Oarai Engineering Center, Ibaraki (Japan). Material Monitoring Section)
IAEA-TECDOC--884, pp:158-168
Advanced 4S (super safe, small and simple) LMR
Minato, A. (Central Research Institute of Electric Power Industry, Tokyo (Japan)); Handa, N. (Toshiba Co-operation, Power Systems and Services Company, Yokohama (Japan))
IAEA-TECDOC--1172, pp:158-177
Creep-fatigue evaluation method for modified 9Cr-1Mo steel
Wada, Y.; Aoto, K. (Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center)
IAEA-TECDOC--933, pp:171-178
Seismic analysis for MONJU core seismic experiments using the SAFA program
Horiuchi, T. (Hitachi Ltd, Tsuchiura, Ibaraki (Japan). Mechanical Engineering Research Lab.)
IAEA-TECDOC--882, pp:175-195
Calculation of fluid flow and heat transfer in a rod bundle with geometrical disturbance based on the 'locally exact' finite-difference scheme
Kriventsev, V.; Ninokata, H. (Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, Tokyo (Japan))
IAEA-TECDOC--1157, pp:175-183
Autoregressive techniques for acoustic detection of in-sodium water leaks
Hayashi, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)
IAEA-TECDOC--946, pp:179-202
Omega program & Neutron science project for developing accelerator hybrid system at JAERI
T.Mukaiyama
IAEA-TC--903.3, pp:179-194
Radiological hazard of long lived spallation products in accelerator driven system
M. Saito, V. Artisyuk, A. Stankovskii
IAEA-TECDOC--1356, pp:185-196
Creep-fatigue evaluation on butt welded joints of type 304 SS
Wada, Y.; Asayama, T.; Hasebe, S.; Kasahara, N. (Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center)
IAEA-TECDOC--933, pp:191-200
An analytical method of evaluating the effect of rod displacement on circumferential temperature and heat flux
distributions -- two and three dimensional treatments
Hishida, Hisashi (Mitsubishi Atomic Power Industries, Inc., Tokyo (Japan))
IAEA-TECDOC--166, pp:194-205
Molten salt reactor benchmark problem to constrain plutonium
Hirakawa, N.; Aboanber, A.I. (Tohoku University, Sendai (Japan)); Mitachi, K. (Toyohashi University of Technology, Toyohashi (Japan)); Misawa, T. (Kyoto University (Japan))
IAEA-TECDOC--1319, pp:198-206
Effect of temperature dependency in material properties to hot spot subfactors
Hishida, Hisashi (Mitsubishi Atomic Power Industries, Inc., Tokyo (Japan))
IAEA-TECDOC--166, pp:206-209
Advanced design of the fast breeder reactor in PNC
Mukaibo, R. (Power Reactor and Nuclear Fuel Development Corp., Plant Engineering Office, Tokyo (Japan). System Engineering Div.)
IAEA-TECDOC--907, pp:237-242
Assessment of 232Th nuclear data through critical experiments using the Kyoto University critical assembly
Shiroya, S.; Unesaki, H.; Misawa, T. (Kyoto University, Osaka (Japan))
IAEA-TECDOC--1319, pp:237-248
JNC viewpoint on fast reactor knowledge preservation
Yokota, Y.; Harrison, P.; Irie, T. (Japan Nuclear Cycle Development Institute (JNC), Ibaraki (Japan))
IAEA-TECDOC--1405, pp:255-260
Hybrid system concepts for nuclear waste transmutation
T.Takizuka, JAERI
IAEA-TC--903.3, pp:351-361
Development of high intensity proton accelerator
M. Mizumoto, J. Kusano, K. Hasegawa, N. Ouchi, H. Oguri, M. Kinsho,
Y. Touchi, Y. Honda, K. Mukugi, H. Ino, F. Noda, N. Akaoka, H. Kaneko,
E. Chishiro. B. Fechner
Japan Atomic Energy Research Institute
Tokai-mum, Naka-gun, Ibaraki-ken 3 19- 11, Japan
IAEA-TC--903.3, pp:363-373
Fast reactor core thermal-hydraulic analyses during transition from forced to natural circulation
Nishimura, M.; Ohshima, H.; Kamide, H. (O-arai Engineering Center, Power Reactor and Nuclear Fuel Development Corporation, O-arai, Ibaraki-ken (Japan))
IAEA-TECDOC--1157, pp:378-395
Reactivity calculations on molten-lead hybrid reactors
J.M.Martinez-Val, M.Perlado, E.Minguez, M.D.Cobo, A.Oda*
E.T.S.l.lndustriales,
Madrid Polytechnic University, Spain
* Visiting researcher from Kyushu University, Japan
IAEA-TC--903.3, pp:399-408
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