Nuclear Techniques ›› 2014, Vol. 37 ›› Issue (12): 120603-120603.doi: 10.11889/j.0253-3219.2014.hjs.37.120603

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Study on the influence of core volume of PB-FHR on coolant temperature reactivity coefficient

SUN Jianyou1,2 ZOU Yang2,3 YAN Rui2 ZHU Guifeng2 LI Guangchao2 CHEN Liang1,2 LI Dongcang1 XU Hongjie2,3   

  1. 1(School of Nuclear Science and Technology, Lanzhou University, Lanzhou 730000, China) 2(Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, Shanghai 201800, China) 3(Key Laboratory of Nuclear Radiation and Nuclear Energy Technology, Chinese Academy of Sciences, Shanghai 201800, China)
  • Received:2014-04-11 Revised:2014-08-11 Online:2014-12-10 Published:2014-12-04

Abstract: Background: The coolant temperature reactivity coefficient (CTRC) of the pebble fluoride-salt-cooled high temperature reactors (PB-FHR) is closely related to the core volume. Purpose: The relationship between the core volume of PB-FHR with 2LiF-BeF2 (7Li concentration: 99.995%) as coolant and the CTRC values are quantitatively analyzed. Methods: The CTRCs of FHR with different core volumes were calculated with the computer code KENO in SCALE5.1. Results: CTRC increases from negative to positive as the core volume increases from 2 m3 to an infinite value. Conclusion: Based on the analysis of the four factor formula, the different CTRC values with variant core volume can be attributed to the influence of the leakage probability, non-leakage probability and thermal utilization factor.

Key words: Core volume, Four factors, Non-leakage probability, Coolant Temperature Reactivity Coefficient (CTRC)