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

SUN Jianyou; ZOU Yang; YAN Rui; ZHU Guifeng; LI Guangchao; CHEN Liang; LI Dongcang; XU Hongjie

doi:10.11889/j.0253-3219.2014.hjs.37.120603

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

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- Study on the influence of core volume of PB-FHR on coolant temperature reactivity coefficient
- NUCLEAR TECHNIQUES Vol. 37, Issue 12, Article number: 120603(2014)
- 作者机构：
  
  1. 兰州大学核科学与技术学院,兰州,730000
  2. 中国科学院上海应用物理研究所嘉定园区,上海,201800
  3. 中国科学院核辐射与核能技术重点实验室,上海,201800
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2014.hjs.37.120603
  CLC：
- Published：04 December 2014
- 稿件说明：
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SUN Jianyou, ZOU Yang, YAN Rui, et al. Study on the influence of core volume of PB-FHR on coolant temperature reactivity coefficient[J]. Nuclear techniques, 2014, 37(12): 120603
DOI：

SUN Jianyou, ZOU Yang, YAN Rui, et al. Study on the influence of core volume of PB-FHR on coolant temperature reactivity coefficient[J]. Nuclear techniques, 2014, 37(12): 120603 DOI： 10.11889/j.0253-3219.2014.hjs.37.120603.

摘要

氟盐冷却球床高温反应堆(Pebble Fluoride-Salt-Cooled High Temperature Reactors

PB-FHR)的冷却剂温度反应性系数与其堆芯活性区的几何尺寸有直接关系，研究选取7Li摩尔含量为99.995%的2LiF-BeF2做冷却剂，对冷却剂温度反应性系数与PB-FHR的堆芯活性区体积的关系进行定量分析。利用SCALE5.1软件对不同堆芯活性区体积的PB-FHR的冷却剂温度反应性系数进行了研究。分析结果表明：堆芯活性区体积越大的PB-FHR，冷却剂温度反应性系数越趋于正值，堆芯活性区体积越小的PB-FHR，冷却剂温度反应性系数越趋于负值。基于四因子公式的分析表明，逃脱共振俘获的概率、不泄漏概率和热中子利用系数在不同堆芯活性区体积的PB-FHR内的差异是影响冷却剂温度反应性系数差异的主要原因。

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. Abstract

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