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JAEA Reports

Study of prediction of fission product behaviours in severe accident; Scoping experiment and basic findings of Cs, Ba and Sr

*; J.Huang*; *; *; *; Yamaguchi, Kenji*; Sugimoto, Jun

JAERI-Tech 98-003, 32 Pages, 1998/02

JAERI-Tech-98-003.pdf:1.12MB

no abstracts in English

Journal Articles

Modified conversion ratio measurement in light water-moderated UO $_{2}$ lattices

Nakajima, Ken;

Nuclear Technology, 113, p.375 - 379, 1996/03

https://doi.org/10.13182/NT96-A35217

Times Cited Count：5 Percentile：45.07(Nuclear Science & Technology)

no abstracts in English

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

Reassessment of fuel failure behavior in the SPERT and PBF experiments for irradiated fuel rods under reactivity initiated accident conditions

*; Ishijima, Kiyomi;

JAERI-M 92-044, 322 Pages, 1992/04

JAERI-M-92-044.pdf:20.75MB

no abstracts in English

JAEA Reports

Developmental verification of the FP behavior evaluation computer code, FPRETAIN; Release and retention of FP from pre-irradiated fuel rods

Yanagisawa, Kazuaki

JAERI-M 89-095, 169 Pages, 1989/06

JAERI-M-89-095.pdf:4.45MB

no abstracts in English

JAEA Reports

Out-pile FP Release Experiment by Heating of Irradiated UO $_{2}$ Pellet

;

JAERI-M 85-199, 16 Pages, 1985/12

JAERI-M-85-199.pdf:0.68MB

no abstracts in English

Presentation/Publication Type

Journal/Book Title

Meeting title

First Author

Keyword

Language

Publication Year

Held year of conference

Study of prediction of fission product behaviours in severe accident; Scoping experiment and basic findings of Cs, Ba and Sr

Modified conversion ratio measurement in light water-moderated UO lattices

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

Reassessment of fuel failure behavior in the SPERT and PBF experiments for irradiated fuel rods under reactivity initiated accident conditions

Developmental verification of the FP behavior evaluation computer code, FPRETAIN; Release and retention of FP from pre-irradiated fuel rods

Out-pile FP Release Experiment by Heating of Irradiated UO Pellet

Modified conversion ratio measurement in light water-moderated UO $_{2}$ lattices

Out-pile FP Release Experiment by Heating of Irradiated UO $_{2}$ Pellet