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Suzuki, Motoe; Uetsuka, Hiroshi; Saito, Hiroaki*
Nuclear Engineering and Design, 229(1), p.1 - 14, 2004/04
Times Cited Count:21 Percentile:75.71(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.
; ; ; ; Kawamura, Hiroshi; ; ; Nakagawa, Tetsuya; ;
JAERI-M 93-206, 48 Pages, 1993/10
no abstracts in English
Harayama, Yasuo; ; ; Nakamura, Jinichi; Uchida, Masaaki
JAERI-M 91-003, 38 Pages, 1991/02
no abstracts in English
Nakayama, Fusao; ; ; ; ;
Proc. on the 2nd Asian Symp. on Research and Reactor, p.1 - 18, 1989/00
no abstracts in English
; ; ;
Japan-China Symp. on Research and Test Reactors, 11 Pages, 1988/00
no abstracts in English
; ; E.Kolstad*
Nihon Genshiryoku Gakkai-Shi, 28(7), p.641 - 657, 1986/00
Times Cited Count:4 Percentile:47.75(Nuclear Science & Technology)no abstracts in English
JAERI-M 84-021, 35 Pages, 1984/02
no abstracts in English
;
JAERI-M 83-228, 14 Pages, 1984/01
no abstracts in English
;
JAERI-M 82-127, 53 Pages, 1982/09
no abstracts in English
JAERI-M 7711, 52 Pages, 1978/06
no abstracts in English