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Soba, A.*; Prudil, A.*; Zhang, J.*; Dethioux, A.*; Han, Z.*; Dostal, M.*; Matocha, V.*; Marelle, V.*; Lasnel-Payan, J.*; Kulacsy, K.*; et al.
Proceedings of TopFuel 2021 (Internet), 10 Pages, 2021/10
Uwaba, Tomoyuki; Nemoto, Junichi*; Ito, Masahiro*; Ishitani, Ikuo*; Doda, Norihiro; Tanaka, Masaaki; Otsuka, Satoshi
Nuclear Technology, 207(8), p.1280 - 1289, 2021/08
Times Cited Count：3 Percentile：34.17(Nuclear Science & Technology)Computer codes for irradiation behavior analysis of a fuel pin and a fuel pin bundle and for coolant thermal hydraulics analysis were coupled into an integrated code system. In the system, each code provides data required by other codes and the analyzed results are shared among them. The system allows for the synthesizing of analyses of thermal, chemical and mechanical behaviors in a fuel subassembly under irradiation. A test analysis was made for a fuel subassembly containing a mixed oxide fuel pin bundle irradiated in a fast reactor. The results of the analysis were presented with transverse cross-sectional images of the fuel subassembly and three-dimensional images of a fuel pin and fuel pin bundle models. For detailed evaluation, various irradiation behaviors of all fuel pins in the subassembly were analyzed and correlated with irradiation conditions.
Kakiuchi, Kazuo; Udagawa, Yutaka; Amaya, Masaki
Annals of Nuclear Energy, 155, p.108171_1 - 108171_11, 2021/06
Times Cited Count：1 Percentile：15.09(Nuclear Science & Technology)Taniguchi, Yoshinori; Udagawa, Yutaka; Amaya, Masaki
Annals of Nuclear Energy, 139, p.107188_1 - 107188_7, 2020/05
Times Cited Count：1 Percentile：11.54(Nuclear Science & Technology)
and chromia-alumina additive fuels under simulated reactivity-initiated accidents; A Comparative analysis with FEMAXI-8Udagawa, Yutaka; Mihara, Takeshi; Taniguchi, Yoshinori; Kakiuchi, Kazuo; Amaya, Masaki
Annals of Nuclear Energy, 139, p.107268_1 - 107268_9, 2020/05
Times Cited Count：3 Percentile：34.17(Nuclear Science & Technology)Dost
l, M.*; Rossiter, G.*; Dethioux, A.*; Zhang, J.*; Amaya, Masaki; Rozzia, D.*; Williamson, R.*; Kozlowski, T.*; Hill, I.*; Martin, J.-F.*
Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 10 Pages, 2018/10
fuel at burnup of 45 GWd/t during simulated Reactivity Initiated Accident (RIA) conditionAmaya, Masaki; Sugiyama, Tomoyuki; Fuketa, Toyoshi
Journal of Nuclear Science and Technology, 41(10), p.966 - 972, 2004/10
Times Cited Count：7 Percentile：45.03(Nuclear Science & Technology)Pulse irradiation simulating RIA condition was carried out for test rod prepared from fuel irradiated in a commercial reactor. After the pulse irradiation, optical microscopy (OM) and scanning electron microscopy (SEM) observations and electron probe micro analysis (EPMA) were conducted for the test rod as a part of destructive tests. Fission gas release behavior during pulse irradiation was investigated by EPMA and puncture test. Xeon depression was observed in the fuel pellet after pulse irradiation at periphery and center region. It is considered that fission gas was mainly released from the pellet center region during pulse irradiation. The amount of xenon release during pulse irradiation was estimated to be 10-12% from the EPMA results and this estimated value was comparable with the puncture test result. Comparing the estimated value with other results of out-of-pile annealing tests, it was concluded that most fission gas, which was accumulated at grain boundary during base irradiation, was released from the center region of test fuel pellet during pulse irradiation.
Suzuki, Motoe; Uetsuka, Hiroshi; Saito, Hiroaki*
Nuclear Engineering and Design, 229(1), p.1 - 14, 2004/04
Times Cited Count：19 Percentile：75.11(Nuclear Science & Technology)Mechanical load on cladding induced by fuel swelling in a high burn-up BWR type rod has been analyzed by a fuel performance code FEMAXI-6. The code has been developed for the analysis of LWR fuel rod behaviors in normal operation and transient conditions using FEM. During a power ramp for the high burn-up rod, instantaneous pellet swelling can significantly exceed the level that is predicted by a "steady-rate" swelling model, causing a large circumferential strain in cladding. This phenomenon has been simulated by a new swelling model to take into account the fission gas bubble growth, and as a result it has been found that the new model can give reasonable predictions on cladding diameter expansion in comparison with post-irradiation data. In addition, a pellet-clad bonding model which has been incorporated in the code to assume firm mechanical coupling between pellet outer surface and cladding inner surface has predicted the generation of bi-axial stress state in the cladding during ramp.
Hatakeyama, Yuichi; Sudo, Kenji; Kanazawa, Hiroyuki
JAERI-Tech 2004-033, 29 Pages, 2004/03
JAERI-Tech-2004-033.pdf:1.65MB
The amount of fission gas (Kr, Xe) in irradiated fuel pellet increases with extending the burn up and that exerts a serious influence upon thermal and mechanical properties of light water reactor fuel. Therefore, the accumulation of the data on the release behavior of fission gas is important in the investigation program of safety and reliability for extended burn up fuel. In the post irradiation examination at the Reactor Fuel Examination Facility in JAERI,the fission gas which released into the plenum region from UO pellet during irradiation has been measured by puncturing test of irradiated fuel rod. The results of puncturing test show the most of fission gas remained in the pellet. It can be seen that the additional release of fission gas might occur under higher burn up and accident conditions. To know the fission gas release behavior from irradiated fuel, the Out Gas analyzer(OGA)which has the performance to heat up the UO pellet stepwise up to 2300
C and to measure the released fission gas instantly from the pellet has been developed and installed at RFEF.
Suzuki, Motoe; Saito, Hiroaki*
JAERI-Data/Code 2003-019, 423 Pages, 2003/12
JAERI-Data-Code-2003-019.pdf:17.7MB
A light water reactor fuel analysis code FEMAXI-6 is an advanced version which has been produced by integrating the former version with a number of improvements. In particular, the FEMAXI-6 code has attained a complete coupled solution of thermal analysis and mechanical analysis, permitting an accurate prediction of pellet-clad gap size and PCMI in high burnup fuel rods. Also, such new models have been implemented as pellet-clad bonding and fission gas bubble swelling, and the coupling with burning analysis code has been enhanced. Furthermore, a number of new materials properties and parameters have been introduced. With these advancements, the FEMAXI-6 code is a versatile tool not only in the normal operation but also in transient conditions. This report describes the design, basic theory, models and numerical method, improvements, and model modification. In order to facilitate effective and wide-ranging application of the code, formats and methods of input/output, and a sample output in an actual form are included.
Takase, Haruhiko*; Tobita, Kenji; Nishio, Satoshi
JAERI-Data/Code 2003-013, 46 Pages, 2003/08
JAERI-Data-Code-2003-013.pdf:1.59MB
no abstracts in English
Hiratsuka, Hajime; Kizu, Kaname; Ichige, Hisashi; Honda, Masao; Iwahashi, Takaaki*; Sasaki, Noboru*; Miya, Naoyuki; Hosogane, Nobuyuki; Oda, Yasushi*; Yoshida, Kazuto*
Purazuma, Kaku Yugo Gakkai-Shi, 76(11), p.1189 - 1197, 2000/11
no abstracts in English
Suzuki, Motoe
JAERI-Data/Code 2000-030, 280 Pages, 2000/09
JAERI-Data-Code-2000-030.pdf:11.06MB
no abstracts in English
fuel discsUne, Katsumi*; Nogita, Kazuhiro*; Shiratori, Tetsuo; Hayashi, Kimio
Journal of Nuclear Materials, 288(1), p.20 - 28, 2000/09
Times Cited Count：19 Percentile：77.84(Materials Science, Multidisciplinary)no abstracts in English
Suzuki, Motoe
Nuclear Engineering and Design, 201(1), p.99 - 106, 2000/09
Times Cited Count：7 Percentile：46.84(Nuclear Science & Technology)no abstracts in English
Song, X. M.*; Sugie, Tatsuo; Yoshino, Ryuji
Purazuma, Kaku Yugo Gakkai-Shi, 76(3), p.282 - 287, 2000/03
no abstracts in English
Suzuki, Motoe; Saito, Hioraki*
HPR-349, 12 Pages, 1998/00
no abstracts in English
Okubo, Tadatsune*; *; Suzuki, Motoe
Kaku Nenryo, (29), p.12 - 13, 1998/00
no abstracts in English
Suzuki, Motoe; Saito, Hioraki*
JAERI-Data/Code 97-046, 210 Pages, 1997/11
JAERI-Data-Code-97-046.pdf:5.41MB
no abstracts in English
Suzuki, Motoe; Saito, Hioraki*
JAERI-Data/Code 97-043, 235 Pages, 1997/11
JAERI-Data-Code-97-043.pdf:5.84MB
no abstracts in English
