Improved core design of the high temperature supercritical-pressure light water reactor

A. Yamaji, K. Kamei, Y. Oka, S. Koshizuka

Research output: Contribution to journalArticle

81 Citations (Scopus)

Abstract

A new coolant flow scheme has been devised to raise the average coolant core outlet temperature of the High Temperature Supercritical-Pressure Light Water Reactor (SCLWR-H). A new equilibrium core is designed with this flow scheme to show the feasibility of an SCLWR-H core with an average coolant core outlet temperature of 530 °C. In previous studies, the average coolant core outlet temperature was limited by the relatively low temperature outlet coolant from the core periphery. In order to achieve an average coolant core outlet temperature of 500 °C, each fuel assembly had to be horizontally divided into four sub-assemblies by coolant flow separation plates, and coolant flow rate had to be adjusted for each sub-assembly by an inlet orifice. However, the difficulty of raising the outlet coolant temperature from the core periphery remained. In this study, a new coolant flow scheme is devised, in which the fuel assemblies loaded on the core periphery are cooled by a descending flow. The new flow scheme has eliminated the need for raising the outlet coolant temperature from the core periphery and removed the coolant flow separation plates from the fuel assemblies.

Original languageEnglish
Pages (from-to)651-670
Number of pages20
JournalAnnals of Nuclear Energy
Volume32
Issue number7
DOIs
Publication statusPublished - 2005 May 1
Externally publishedYes

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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