The axial power distribution validation of the SCWR fuel assembly with coupled neutronics-thermal hydraulics method

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• 作者：Xi Xi ; Zejun Xiao ; ^{fabulous_2012@sina.com} ; Xiao Yan ; Yongliang Li ; Yanping Huang
• 刊名：Nuclear Engineering and Design
• 出版年：2013
• 出版时间：May, 2013
• 年：2013
• 卷：258
• 期：Complete
• 页码：157-163
• 全文大小：1129 K

文摘

SCWR (super critical water reactor) is one of the IV generation nuclear reactors in the world. In a typical SCWR the water enters the reactor from the cold leg with a temperature of 280 ¡ãC and then leaves the core with a temperature of 500 ¡ãC. Due to the sharp change in temperature, there is a huge density change of the water along the axial direction of the fuel assembly (FA), which will affect the moderating power of the water. So the axial power distribution of the SCWR FA could be different from the traditional PWR FA.In this paper, it is the first time that the thermal hydraulics code CFX and neutronics code MCNP are used to analyze the axial power distribution of the SCWR FA. First, the factors in the coupled method which could affect the result are analyzed such as the initialization value or the partition method especially in the MCNP code. Then the axial power distribution of the Europe HPLWR FA is obtained by the coupled method with the two codes and the result is compared with that obtained by Waata and Reiss. There is a good agreement among the three kinds of results. At last, this method is used to calculate the axial power distribution of the Chinese SCWR (CSR1000) FA. It is found the axial power profile of the CSR1000 FA is not so sensitive to the change of the moderator density.