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

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

研究成果: Article

80 引用 (Scopus)

抄録

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.

元の言語English
ページ(範囲)651-670
ページ数20
ジャーナルAnnals of Nuclear Energy
32
発行部数7
DOI
出版物ステータスPublished - 2005 5
外部発表Yes

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Light water reactors
Coolants
water
Temperature
temperature
Flow separation
reactor
Orifices
Flow rate

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Waste Management and Disposal

これを引用

Improved core design of the high temperature supercritical-pressure light water reactor. / Yamaji, Akifumi; Kamei, K.; Oka, Y.; Koshizuka, S.

:: Annals of Nuclear Energy, 巻 32, 番号 7, 05.2005, p. 651-670.

研究成果: Article

Yamaji, Akifumi ; Kamei, K. ; Oka, Y. ; Koshizuka, S. / Improved core design of the high temperature supercritical-pressure light water reactor. :: Annals of Nuclear Energy. 2005 ; 巻 32, 番号 7. pp. 651-670.
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