Development of sub-channel code SACoS and its application in coupled neutronics/thermal hydraulics system for SCWR

Khurrum Saleem Chaudri, Yali Su, Ronghua Chen, Wenxi Tian, Guanghui Su, Suizheng Qiu*

*この研究の対応する著者

研究成果: Article査読

28 被引用数 (Scopus)

抄録

Supercritical Water Reactor (SCWR) is one of the promising reactors from the list of fourth generation of nuclear reactors. High thermal efficiency and low cost of electricity make it an attractive option in the era of growing energy demand. An almost seven fold density variation for coolant/moderator along the active height does not allow the use of constant density assumption for design calculations, as used for previous generations of reactors. The advancement in computer technology gives us the superior option of performing coupled analysis. Thermal hydraulics calculations of supercritical water systems present extra challenges as not many computational tools are available to perform that job. This paper introduces a new sub-channel code called Sub-channel Analysis Code of SCWR (SACoS) and its application in coupled analyses of High Performance Light Water Reactor (HPLWR). SACoS can compute the basic thermal hydraulic parameters needed for design studies of a supercritical water reactor. Multiple heat transfer and pressure drop correlations are incorporated in the code according to the flow regime. It has the additional capability of calculating the thermal hydraulic parameters of moderator flowing in water box and between fuel assemblies under co-current or counter current flow conditions. Using MCNP4c and SACoS, a coupled system has been developed for SCWR design analyses. The developed coupled system is verified by performing and comparing HPLWR calculations. The results were found to be in very good agreement. Significant difference between the results was seen when Doppler feedback effect was included in the coupled calculations. This difference is due to the use of different values of fuel temperature to include Doppler feedback in our and reference coupled systems. This also lays emphasis on the use of true representative values of critical parameters in the design calculations to get the real picture of conditions rather than over or under estimated values.

本文言語English
ページ(範囲)37-45
ページ数9
ジャーナルAnnals of Nuclear Energy
45
DOI
出版ステータスPublished - 2012 7月

ASJC Scopus subject areas

  • 原子力エネルギーおよび原子力工学

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