Refine your search:     
Report No.
 - 
Search Results: Records 1-5 displayed on this page of 5
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

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:19 Percentile:75.17(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.

Journal Articles

Density, porosity and grain size, 2; Irradiated ROX fuels to burn-up of 28%FIMA

Yanagisawa, Kazuaki; Yamashita, Toshiyuki; Kanazawa, Hiroyuki; Amano, Hidetoshi; Muromura, Tadasumi

Journal of Nuclear Science and Technology, 36(12), p.1153 - 1159, 1999/12

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Irradiation behavior of microspheres of U-Zr alloys

Ogawa, Toru; *; Ito, Akinori; ; Sekino, Hajime; Nishi, Masahiro; Ishikawa, Akiyoshi; Akabori, Mitsuo

Journal of Alloys and Compounds, 271-273, p.670 - 675, 1998/00

 Times Cited Count:7 Percentile:49.87(Chemistry, Physical)

no abstracts in English

Journal Articles

Irradiation behavior of high uranium-density alloys in the plate fuels

Ugajin, Mitsuhiro; Ito, Akinori; Akabori, Mitsuo; Ooka, Norikazu;

Journal of Nuclear Materials, 254(1), p.78 - 83, 1998/00

 Times Cited Count:22 Percentile:89.86(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Fission gas release from rock-like fuels, PuO$$_{2}$$-ZrO$$_{2}$$(Y){or ThO$$_{2}$$}-Al$$_{2}$$O$$_{3}$$-MgO at burn-up of 20 MWd/kg

Yanagisawa, Kazuaki; Omichi, Toshihiko; Kanazawa, Hiroyuki; Amano, Hidetoshi; Yamahara, Takeshi

JAERI-Research 97-085, 31 Pages, 1997/11

JAERI-Research-97-085.pdf:2.38MB

no abstracts in English

5 (Records 1-5 displayed on this page)
  • 1