Principle of rationalizing the criteria for abnormal transients of the Super LWR with fuel rod analyses

A. Yamaji*, Y. Oka, Y. Ishiwatari, J. Liu, M. Suzuki

*この研究の対応する著者

研究成果: Article査読

13 被引用数 (Scopus)

抄録

A detailed fuel rod design is carried out for the first time in the development of Supercritical-pressure Light Water Reactor (Super LWR). The fuel rod design is similar to that of LWR, consisting of UO2 pellets, a gas plenum and a Stainless Steel Cladding. The principle of rationalizing the criteria for abnormal transients of the Super LWR is developed. The fuel rod integrities can be assured by preventing plastic strains on the cladding, preventing the cladding buckling collapse, and keeping the pellet centerline temperature below its melting point. The FEMAXI-6 fuel analysis code is used to evaluate the fuel rod integrities in abnormal transient conditions. Detailed analyses have shown that allowable limits to the maximum fuel rod power and maximum cladding temperature can be determined to assure the fuel integrities. These limits may be useful in the plant safety analyses to confirm the fuel integrities during abnormal transients.

本文言語English
ページ(範囲)984-993
ページ数10
ジャーナルAnnals of Nuclear Energy
33
11-12
DOI
出版ステータスPublished - 2006 8月
外部発表はい

ASJC Scopus subject areas

  • 原子力エネルギーおよび原子力工学

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