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A MIXED CORE FOR SUPERCRITICAL WATER-COOLED REACTORS
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  • A MIXED CORE FOR SUPERCRITICAL WATER-COOLED REACTORS
  • A MIXED CORE FOR SUPERCRITICAL WATER-COOLED REACTORS
저자명
Cheng. Xu,Liu. Xiao-Jing,Yang. Yan-Hua
간행물명
Nuclear engineering and technology : an international journal of the Korean Nuclear Society
권/호정보
2008년|40권 2호|pp.117-126 (10 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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기타
이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
서지반출

기타언어초록

In this paper, a new reactor core design is proposed on the basis of a mixed core concept consisting of a thermal zone and a fast zone. The geometric structure of the fuel assembly of the thermal zone is similar to that of a conventional thermal supercritical water-cooled reactor(SCWR) core with two fuel pin rows between the moderator channels. In spite of the counter-current flow mode, the co-current flow mode is used to simplify the design of the reactor core and the fuel assembly. The water temperature at the exit of the thermal zone is much lower than the water temperature at the outlet of the pressure vessel. This lower temperature reduces the maximum cladding temperature of the thermal zone. Furthermore, due to the high velocity of the fast zone, a wider lattice can be used in the fuel assembly and the nonuniformity of the local heat transfer can be minimized. This mixed core, which combines the merits of some existing thermal SCWR cores and fast SCWR cores, is proposed for further detailed analysis.