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

Akifumi Yamaji, Kazuhiro Kamei, Yoshiaki Oka, Seiichi Koshizuka

Research output: Chapter in Book/Report/Conference proceedingConference contribution

6 Citations (Scopus)

Abstract

An equilibrium core of High Temperature Supercritical-Pressure Light Water Reactor is designed. Part of the feed water flows down the fuel assemblies loaded at the peripheries of the core, before flowing up the fuel channels in the inner region of the core. With this new flow scheme, the average coolant core outlet temperature is increased from 500C of the past design to 550C. The coolant flow rate for each fuel assembly is fixed by the inlet orifices to match the power generation. The maximum fuel rod cladding surface temperature is 650C.

Original languageEnglish
Title of host publicationProceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04
Pages509-517
Number of pages9
Publication statusPublished - 2004 Dec 1
Externally publishedYes
EventProceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04 - Pittsburgh, PA, United States
Duration: 2004 Jun 132004 Jun 17

Publication series

NameProceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04

Other

OtherProceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04
CountryUnited States
CityPittsburgh, PA
Period04/6/1304/6/17

ASJC Scopus subject areas

  • Engineering(all)

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  • Cite this

    Yamaji, A., Kamei, K., Oka, Y., & Koshizuka, S. (2004). Improved core design of high temperature supercritical-pressure light water reactor. In Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04 (pp. 509-517). (Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04).