压水堆燃料组件内放射性源项计算与分析

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

Nuclear Techniques ›› 2014, Vol. 37 ›› Issue (04): 40601-040601.doi: 10.11889/j.0253-3219.2014.hjs.37.040601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles Next Articles

Calculation and analysis of radioactive source term in PWR assemblies

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

(Nuclear and Radiation Safety Center, Beijing 100082, China)

Received:2013-10-12 Revised:2014-01-17 Online:2014-04-10 Published:2014-04-11

Abstract

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.

Key words: Fuel assembly, ORIGEN-S, ENDF/B, Source term

CHEN Haiying, QIAO Yahua, WANG Shaowei, CHEN Yan, LAN Bing, ZHANG Chunming. Calculation and analysis of radioactive source term in PWR assemblies[J].Nuclear Techniques, 2014, 37(04): 40601-040601.

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Calculation and analysis of radioactive source term in PWR assemblies

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