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Ijima, Takashi; ; Matsumoto, Mitsuo; *
JNC TN3410 2000-002, 93 Pages, 2000/01
Fugen Nuclear Power Station ("Fugen") is a prototype Advanced Thermal Reactor (ATR), it has been demonstrated the plutonium utilization by loading many Mixed Oxide Fuels (MOX) since the reactor start up March 1979, and no fuel defect had been occurred, The MOX fuel assemblies has the high reliability and has been loaded more than 700 fuel assemblies. This is the largest in the world as a thermal neutron reactor. However, "Fugen" is planning to stop its operation in the year 2003, because the role of the Fugen almost finished. Therefore, we are going to summarize the ATR project including the Plutonium utilization experience. This paper is summarized as part of the experience.
Adachi, Takeo; Ito, Mitsuo; ; Takeishi, Hideyo; ; ; ; ; ; ; et al.
JAERI-Tech 98-053, 46 Pages, 1998/12
no abstracts in English
; Yamaguchi, Takashi; ; Matsumoto, Mitsuo
Proceedings of International Conference on Future Nuclear Systems (GLOBAL'97), 0 Pages, 1997/00
None
; ; ; ; Kobayashi, Tetsuro*; ; Sugawara, Satoru; Matsumoto, Mitsuo
Donen Giho, (94), p.36 - 52, 1995/06
None
; Abe, Tomiyuki; Matsumoto, Mitsuo
ANP '92, 19-1 Pages, 1992/10
; *; ; ; ; Matsumoto, Mitsuo
PNC TN8410 92-187, 21 Pages, 1992/05
Computer code for fuel temperature evaluation of LMFBR at early burnup has been developed. On fule temperature evaluation, especially at early burnup, the fuel restructuring model and the gap conductance medel are important. These models which are installed in the temperature evaluation code, were verified based on the results of irradiation tests using the foreign fast reactor and "JOYO". This paper describes the essential parts of the models and the functions of the code (DIRAD) which is used for the fuel temperature evaluation at early burnup of LMFBR such as the prototype fast breeder reactor "MONJU".
; ; ; Matsumoto, Mitsuo
ANP 92 INTERNATIONAL CONFTY OF ADVANCED NUCLEAR P, 2, 19-1 Pages, 1992/00
None
Komoda, S.; Nakae, Nobuo; Matsumoto, Mitsuo
Journal of Nuclear Materials, 188, p.319 - 322, 1992/00
Times Cited Count:0 Percentile:0.01(Materials Science, Multidisciplinary)Abe, Tomiyuki; Nakae, Nobuo; Kodato, Kazuo; Matsumoto, Mitsuo
Journal of Nuclear Materials, 188, p.154 - 161, 1992/00
Times Cited Count:6 Percentile:53.1(Materials Science, Multidisciplinary)Shiratori, Yoshitake; Furubayashi, Toshiyuki; Matsumoto, Mitsuo
PNC TN3410 91-031, 47 Pages, 1991/11
ugen has been operating safely and smoothly for twelve years using mainly plutonium-uranium mixed oxide (mox) fuels, and much operation data has been accumulated during this time. Fugen's core management has been established, and its core characteristics have been evaluated through the operation. the effect of am accumulation and plutonium composition ratio must be considered when many mox fuels are used in a thermal reactor. Calculation accuracy of core analysis code is good and core characteristics are well evaluated by the consideration of these factors. Fuel inspection shows that there is no big difference between mox and uo fuel.
Oteru, Shigeru; Matsumoto, Mitsuo; Deshimau, Takehide; Tai, Ichio*; Hanai, Kohi*; Kameda, Akiyuki*
PNC TN3410 88-015, 10 Pages, 1988/06
A long-life in-core neutron detector was developed from 1973 through 1978 and since then, it has been applied to the prototype heavy water reactor "Fugen" as a local power monitor. More than 10 year's operation experience of the detector proved its performance as was expected. The detector is a fission chamber of regenerative type whose tube is made of zircaloy-2 metal for neutron economy. In-core neutron detectors for the local power monitor are placed in heavy water moderator of 50 c. The in-core conditions bring a high level thermal neutron flux environment. It tends to hurt the lineality and shorten the life time of the detectors because of rapid burnup of the neutron conversion material(U)in thedetector compared to the light water reactors.These problems were solved by some improvements and it was demonstrated that the detector had the performance of high linearity and long-life characteristics.
; ; ; Matsumoto, Mitsuo
Nihon Genshiryoku Gakkai-Shi, 29(5), p.368 - 384, 1987/05
Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)Matsumoto, Mitsuo; Ogawa T*; Ishii Y*; Yamagis*; Suzuki*
PNC TN241 79-30VOL3, 18 Pages, 1979/09
The full mock-up operation test of Control Rod Drive Mechanism (CRDM) for "MONJU" have been carried on since 1972 in OEC of PNC. Welded type bellows were adopted for CRDM as the boundary between sodium and atmosphere. In design, two different locations were considered for bellows, one in sodium and the other in argon gas with sodium vapor and some experiences on the bellows have been obtained. Besides the prototype tests of CRDM, several R&D on CRDM bellows, such as environment effect test and endurance test are conducted.
JRR-2 Control Office; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Morozumi, Minoru; Kambayashi, Yuichiro; Shitomi, Hajimu; Kokanezawa, Takashi; et al.
JAERI 1027, 57 Pages, 1962/09
no abstracts in English
JRR-2 Critical Experiments Group; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Morozumi, Minoru; Kambayashi, Yuichiro; Shitomi, Hajimu; Kokanezawa, Takashi; et al.
JAERI 1025, 62 Pages, 1962/03
no abstracts in English