采用SCALE计算氟盐冷却高温堆产氚量的一些问题

彭 超; 朱兴望; 张国庆; 何兆忠; 乔延波; 陈 堃

doi:10.11889/j.0253-3219.2015.hjs.38.080601

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采用SCALE计算氟盐冷却高温堆产氚量的一些问题

核能科学与工程 | 更新时间：2021-03-03

- 采用SCALE计算氟盐冷却高温堆产氚量的一些问题
  封面论文
- Issues in the calculation of the tritium production of the fluoride-salt-cooled high-temperature reactors using SCALE
- 核技术 2015年38卷第8期文章编号：080601
- 作者机构：
  
  1. 中国科学院上海应用物理研究所嘉定园区,上海,201800
  2. 中国科学院大学,北京,100049
- 作者简介：
- 基金信息：
  
  中国科学院战略性先导科技专项项目(No.XDA02050100)资助()
- DOI：10.11889/j.0253-3219.2015.hjs.38.080601
  中图分类号：
- 纸质出版日期：2015-08-13
- 稿件说明：
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彭超, 朱兴望, 张国庆, 等. 采用SCALE计算氟盐冷却高温堆产氚量的一些问题[J]. 核技术, 2015,38(8):080601

PENG Chao, ZHU Xingwang, ZHANG Guoqing, et al. Issues in the calculation of the tritium production of the fluoride-salt-cooled high-temperature reactors using SCALE [J]. Nuclear techniques, 2015, 38(8): 080601
彭超, 朱兴望, 张国庆, 等. 采用SCALE计算氟盐冷却高温堆产氚量的一些问题[J]. 核技术, 2015,38(8):080601 DOI： 10.11889/j.0253-3219.2015.hjs.38.080601.

PENG Chao, ZHU Xingwang, ZHANG Guoqing, et al. Issues in the calculation of the tritium production of the fluoride-salt-cooled high-temperature reactors using SCALE [J]. Nuclear techniques, 2015, 38(8): 080601 DOI： 10.11889/j.0253-3219.2015.hjs.38.080601.

摘要

氟盐冷却高温堆(Fluoride-salt-cooled High-temperature Reactor

FHR)是以熔融的氟盐(2LiF-BeF2

FLiBe)作为冷却剂、TRISO (Tri-structural Isotropic)颗粒为燃料、石墨为慢化剂的热中子反应堆。FLiBe冷却剂中的6Li、7Li、9Be和19F等核素在中子的辐照下产生氚。氚于高温下在金属材料中具有较强的渗透性，可能对操作人员及公众造成放射性危害。氚与F原子结合生成具有强腐蚀性的TF，可能影响结构材料的力学性能和使用寿命。本文采用SCALE5.1和SCALE6（包括6.1、6.1.2和目前最新发布版本6.1.3，后文若无特别说明，SCALE6均指此三个版本）中的TRITON (Transport Rigor Implemented with Time-dependent Operation for Neutronic depletion)模块计算了典型FHR的产氚量。计算结果表明，在Li元素的产氚计算中，SCALE6的TRITON模块由于对Li元素处理不当，给计算结果带来较大差异，影响了计算的正确性。在计算9Be和19F的产氚量时，由于不同版本的SCALE采用不同的反应通道等原因，计算结果也存在差异。综合分析表明，通过SCALE计算FHR产氚量时应当优先采用SCALE6，为修正Li元素处理不当的问题，需使用TRITON中经COUPLE子模块更新整合后的截面库（TRITON 默认为ft33f001）来单独运行ORIGEN-S模块。

Abstract

Background: The Fluoride-salt-cooled high-temperature reactor (FHR) is a thermal reactor using molten salt (2LiF-BeF2

FLiBe) as coolant and TRISO (Tri-structural Isotropic) as fuel and graphite as moderator. Isotopes

such as 6Li

7Li

9Be and 19F in the FLiBe coolant

generate tritium under the neutron irradiation. Tritium can easily permeate through metal at high temperature and may be a radiation source to the workers and public. Tritium can also react with F and create TF

which is highly corrosive and may cause damage to the structural materials. Purpose: We used different versions of SCALE to calculate the tritium production of a typical FHR and analyzed the difference among the computational results. Methods: We have created 3D models using the same FHR design parameters in SCALE. Results: The results show that in the calculation of tritium production from lithium

the TRITON (Transport Rigor Implemented with Time-dependent Operation for Neutronic depletion) module of SCALE6 handles the lithium element incorrectly and introduces significant differences compared with the previous versions of SCALE. When we calculate the tritium production from 9Be and 19F

different versions of SCALE give different results because the reactions are defined differently. Conclusion: Our analyses show that when SCALE is used to calculate the tritium production of the FHR

SCALE6 is the preferred version. However

the temporary file

ft33f001

created by TRITON as the cross section library

and ORIGEN-S can be used to calculate the tritium production in order to correct the mishandling of lithium element in SCALE6. Abstract

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