Application of 3-D Core Fuel Management Transport Program for HFETR

ZHU Lei; ZHANG Tengfei; SUN Shouhua; XIANG Yuxin; WU Hongchun; ZHENG Youqi; LI Jian

doi:10.13832/j.jnpe.2015.06.0010

Volume 36 Issue 6

Feb. 2025

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ZHU Lei, ZHANG Tengfei, SUN Shouhua, XIANG Yuxin, WU Hongchun, ZHENG Youqi, LI Jian. Application of 3-D Core Fuel Management Transport Program for HFETR[J]. Nuclear Power Engineering, 2015, 36(6): 10-13. doi: 10.13832/j.jnpe.2015.06.0010

Citation:

ZHU Lei, ZHANG Tengfei, SUN Shouhua, XIANG Yuxin, WU Hongchun, ZHENG Youqi, LI Jian. Application of 3-D Core Fuel Management Transport Program for HFETR[J]. Nuclear Power Engineering, 2015, 36(6): 10-13. doi: 10.13832/j.jnpe.2015.06.0010

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Application of 3-D Core Fuel Management Transport Program for HFETR

doi: 10.13832/j.jnpe.2015.06.0010

1. Nuclear Power Institute of China, Chengdu, 610041, China;
2. School of Energy and Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China

Received Date: 2015-03-14
Rev Recd Date: 2015-10-08

Available Online: 2025-02-15

Abstract

Abstract

This paper introduces the development backgrounds of HEFT, which is a 3-D core fuel management transport calculation program of HFETR, introduces the principle and function of the three main modules of HEFT, that is HEFT-lat, HEFT-core and HEFT-int, and the calculation method of lattice parameter and reactor loop calculation method are described. By the follow-up calculation of 81-I to 89-II of HFETR core and the comparison of initial critical keff, the control rod position during shutting down and the neutron flux, the calculation deviation is obtained. The result shows the validity of the HEFT code, the lattice and reactor core calculation model. Thus, HEFT has already successfully applied to the fuel management calculation of HFETR.
- HFETR,
- Fuel Management,
- HEFT