Calculation and analysis of radioactive source term in PWR assemblies

CHEN Haiying; QIAO Yahua; WANG Shaowei; CHEN Yan; LAN Bing; ZHANG Chunming

doi:10.11889/j.0253-3219.2014.hjs.37.040601

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Calculation and analysis of radioactive source term in PWR assemblies

更新时间：2021-03-03

- Calculation and analysis of radioactive source term in PWR assemblies
- NUCLEAR TECHNIQUES Vol. 37, Issue 4, Article number: 040601(2014)
- 作者机构：
  
  环境保护部核与辐射安全中心,北京,100082
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2014.hjs.37.040601
  CLC：
- Published：11 April 2014
- 稿件说明：
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CHEN Haiying, QIAO Yahua, WANG Shaowei, et al. Calculation and analysis of radioactive source term in PWR assemblies[J]. Nuclear techniques, 2014, 37(4): 040601
DOI：

CHEN Haiying, QIAO Yahua, WANG Shaowei, et al. Calculation and analysis of radioactive source term in PWR assemblies[J]. Nuclear techniques, 2014, 37(4): 040601 DOI： 10.11889/j.0253-3219.2014.hjs.37.040601.

摘要

反应堆堆芯中核燃料发生裂变时，产生了大量的放射性物质，给核电厂环境保护带来了挑战。燃料组件内的放射性源项是反应堆冷却剂放射性源项屏蔽设计、事故源项分析和放射性后果评估的基础。本文针对压水堆开展燃料组件内放射性源项的计算研究，采用ORIGEN-S程序，建立合适的计算方法，研究不同燃耗下燃料组件内源项计算结果的差异，并对比分析了不同版本的ENDF/B截面库对计算结果产生的影响，为压水堆燃料组件内放射性源项的计算提供参考。

Abstract

Background: When fission occurs in fuel of reactor core

it produces a large amount of radioactive materials

which may cause harm to the environment and human health. Purpose: The radioactive materials in fuel could provide input data for shielding design of reactor coolant radioactive source term

analysis of accident source term and radioactive consequence assessment. Methods: The calculation of radioactive source in fuel was studied for pressurized water reactor

the calculation methods and models were established using ORIGEN-S

and the difference of nuclides radioactivity under different burnup was also studied. The effect of different versions of ENDF/B cross-section database on the calculation results was analyzed

so as to provide a basis for the calculation of radioactive source in fuel. Results: The results showed that the method established by ORIGEN-ARP was more suitable for calculating radioactive source term in fuel assemblies and the different versions of ENDF/B database had a great impact on radioactivity calculation. Conclusion: Based on the ENDF/B-VII database

using ORIGEN-ARP to calculate radioactive source term in fuel assemblies could not only improve efficiency

but also improve the calculation accuracy.Cited

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Related Author

LAN Bing

CHEN Yan

WANG Shaowei

GU Hanyang

LI Leilei

LIU Maolong

NI Song

WANG Xiaowen

Related Institution

Department of Mechanical Engineering, City University of Hong Kong

School of Nuclear Science and Engineering, Shanghai Jiao Tong University

Hunan Engineering & Technology Research Center for Virtual Nuclear Reactor, University of South China

School of Nuclear Science and Technology, University of South China

Institute of Nuclear Energy Safety Technology, Hefei Institutes of Physical Science, Chinese Academy of Sciences

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