竹制燃料：necp竹制压水堆乏燃料核素成分评价代码

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-04-10 DOI:10.1016/j.nucengdes.2025.114047

Yunzhao Li , Songzhe Wang , Yuancheng Zhou , Senhan Yang , Ruizhi Shao , Liangzhi Cao , Tian Chen , Miao Yu , Zeng Shao , Guoming Liu

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引用次数: 0

摘要

为了准确获取乏燃料中的核素组成，开发了一个名为Bamboo-SFuel的核素组成计算程序，作为压水堆堆芯分析软件NECP-Bamboo的一个新组件。它可以在不同的损耗数据文件库之间切换，包括在 Bamboo-Lattice 晶格代码中包含 233 个核素的数据文件库、包含 1547 个核素的数据文件库和包含 3838 个核素的数据文件库。国内现有程序的缺陷，如数据库中核素种类不全、辐照过程模拟不完整等，限制了乏燃料后处理安全分析的可靠性和经济性。利用辐照后实验（PIE）的测量数据对核素组成进行了定量验证和分析。通过与 SCALE 软件包的计算结果进行比较，验证了该程序源项计算的准确性，并探讨了不同耗尽数据库对核素组成和源项计算结果的影响。数值结果得出了令人鼓舞的结论。(1）Bamboo-SFuel 可以准确分析商业压水堆乏燃料组件在不同辐照条件下的放射性核素组成和放射源项。(2）不同核素数量的耗损数据文库对重要核素组成的计算结果影响较小，但对总放射源项的计算结果影响较大。(3) 基于内置的包含 1547 种核素的耗损数据集，该程序可同时提供可靠的乏燃料放射源分析和辐射安全分析所关注的重要核素成分分析。

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Bamboo-SFuel: A nuclide composition evaluation code for PWR spent fuel in NECP-Bamboo

To accurately obtain the nuclide composition in spent fuel, a nuclide composition calculation program named Bamboo-SFuel has been developed as a new component in the PWR-core analysis software NECP-Bamboo. It can switch between different depletion data libraries, including one with 233 nuclides in the lattice code Bamboo-Lattice, the one with 1547 nuclides, or the one with 3838 nuclides. The shortcomings of existing domestic procedures, such as incomplete nuclide types in the data library and incomplete simulation of the irradiation process, limit the reliability and economy of the safety analysis of spent fuel reprocessing. The nuclide composition was quantitatively verified and analyzed using the measured data of Post-Irradiation Experiments (PIE). The source term calculation accuracy of the program was verified by comparing with the calculation results of the SCALE package, and the impact of different depletion data libraries on the nuclide composition and source term calculation results was also explored. Encouraging conclusions have been drawn from the numerical results. (1) Bamboo-SFuel can accurately analyze the radionuclide composition and radioactive source term of spent fuel assemblies of commercial PWR under different irradiation conditions. (2) The depletion data library with different numbers of nuclides has little influence on the calculation results of important nuclide composition, but has a great influence on the total radioactive source term calculation results. (3) Based on the built-in depletion data library containing 1547 nuclides, this program can simultaneously provide reliable radioactive source analysis of spent fuel and important nuclide composition concerned by radiation safety analysis.

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.