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Journal Articles

Analysis of mechanical load on cladding induced by fuel swelling during power ramp in high burn-up rod by fuel performance code FEMAXI-6

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.

JAEA Reports

Development of pressure transducer re-instrumentating technique, II; Remote welding and fabrication techniques

; ; ; ; Kawamura, Hiroshi; ; ; Nakagawa, Tetsuya; ;

JAERI-M 93-206, 48 Pages, 1993/10

JAERI-M-93-206.pdf:2.31MB

no abstracts in English

JAEA Reports

Thermal analysis of boiling water capsule

Harayama, Yasuo; ; ; Nakamura, Jinichi; Uchida, Masaaki

JAERI-M 91-003, 38 Pages, 1991/02

JAERI-M-91-003.pdf:1.22MB

no abstracts in English

Journal Articles

The Present situation of power ramping test at the JMTR

Nakayama, Fusao; ; ; ; ;

Proc. on the 2nd Asian Symp. on Research and Reactor, p.1 - 18, 1989/00

no abstracts in English

Journal Articles

Power ramp test for LWR fuel in the JMTR

; ; ;

Japan-China Symp. on Research and Test Reactors, 11 Pages, 1988/00

no abstracts in English

Journal Articles

Study of pellet-cladding interaction on light water reactor fuel, (I); PWR type fuel rod

; ; 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

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