不同燃耗计算模型对商用压水堆乏燃料组件核素成分的影响分析

陈熙荣; 谢金森; 于涛; 倪梓宁; 邓年彪; 邵增; 谢浩然

doi:10.11884/HPLPB202335.230010

不同燃耗计算模型对商用压水堆乏燃料组件核素成分的影响分析

doi: 10.11884/HPLPB202335.230010

陈熙荣^{1, 2,},
谢金森^{1, 2},
于涛^{1, 2, ,},
倪梓宁^{1, 2},
邓年彪^{2, 3},
邵增⁴,
谢浩然^{1, 2}

1.
南华大学核科学技术学院，湖南衡阳 421001
2.
南华大学核能与核技术工程虚拟仿真实验教学中心，湖南衡阳 421001
3.
南华大学资源环境与安全学院，湖南衡阳 421001
4.
中国核电工程有限公司，北京 100840

详细信息

作者简介:
陈熙荣，1169189719@qq.com

通讯作者:
于　涛， yutao29@sina.com

中图分类号: TL32;TL329
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- 文章访问数: 723
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- PDF下载量: 90
- 被引次数: 0
出版历程
- 收稿日期: 2023-01-13
- 修回日期: 2023-02-18
- 网络出版日期: 2022-11-24
- 刊出日期: 2023-04-07

Analysis of different burnup calculation models on nuclide components of spent fuel assembly in commercial pressurized water reactor

Chen Xirong^{1, 2
,},
Xie Jinsen^{1, 2},
Yu Tao^{1, 2
, ,},
Ni Zining^{1, 2},
Deng Nianbiao^{2, 3},
Shao Zeng⁴,
Xie Haoran^{1, 2}

1.
School of Nuclear Science and Technology, University of South China, Hengyang 421001, China
2.
Virtual Simulation Experiment Teaching Center on Nuclear Energy and Technology, University of South China, Hengyang 421001, China
3.
School of Resource Environment and Safety Engineering, University of South China, Hengyang 421001, China
4.
China Nuclear Power Engineering Co., Ltd, Beijing 100840, China

摘要

摘要: 燃耗计算精度对提高乏燃料贮存效率有着重要影响，在应用燃耗信用制时，燃耗计算得到的核素成分偏差决定了乏燃料贮存的临界安全裕量。不同燃耗计算模型所得到的核素成分偏差各不相同，为提高燃耗计算精度，提出了一种装载不同燃料富集度的多组件燃耗计算模型，并使用不同燃耗计算模型分别对TMI-1反应堆NJ07OG组件中的6个样本进行了计算、对比和分析。结果表明，相比其他模型，考虑不同燃料富集度的多组件模型得到的²³⁵U、²³⁸U和²³⁹Pu等核素平均相对偏差更接近于零且6个样本的相对偏差分布更为平均。
- 燃耗计算模型 /
- 乏燃料实验基准数据 /
- 核素成分偏差 /
- 燃耗信任制
Abstract: Burnup credit has an important impact on improving the efficiency of spent fuel storage. In the burnup credit, the burnup calculation model can affect the nuclide composition deviation, and the more accurate the nuclide composition, the lower the critical safety margin for spent fuel storage. To improve the accuracy of the burnup calculation, a multi-assembly burnup calculation model loaded with different fuel enrichment is proposed in this paper. Six samples of TMI-1 reactor NJ07OG assemblies were calculated, compared and analyzed by using different burnup calculation models. The results show that the average relative deviations of ²³⁵U, ²³⁸U and ²³⁹Pu obtained from the multi-assembly burnup model with different fuel enrichment are closer to zero and the relative deviations are more evenly distributed among the six samples than that of other models.
- burnup calculation model /
- SFCOMPO-2.0 /
- nuclide deviation /
- burnup credit

HTML全文

图 1 TMI-1压水堆NJ07OG组件布置图

Figure 1. Assembly NJ07OG layout of PWR TMI-1

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图 2 样本轴向位置

Figure 2. Axial position of the sample

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图 3 样本辐照历史图

Figure 3. Irradiation history of samples

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图 4 TMI-1压水堆NJ07OG组件周围燃料布置图

Figure 4. Layout of other assemblies around the TMI-1 pressurized water reactor NJ07OG assembly

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图 5 四种不同的燃耗计算模型图

Figure 5. Four different burnup calculation models

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图 6 主要核素的不同模型计算值相对偏差对比图

Figure 6. Comparison of relative deviations of calculated values for major nuclides

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图 7 不同模型的平均相对偏差图

Figure 7. Comparison of the average relative deviations

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表 1 燃料组件几何参数表

Table 1. Fuel assembly geometric parameters (mm)

fuel pellet inner diameter	clad inner diameter	clad outer diameter	cell pitch	absorber rod pellet diameter	absorber rod cladding inner diameter
9.40	9.58	10.92	14.43	8.64	9.14

absorber rod cladding outer diameter	guide tube inner diameter	guide tube outer diameter	instrument tube inner diameter	instrument tube outer diameter	assembly pitch
10.92	12.65	13.46	11.2	12.52	218.11

下载: 导出CSV

表 2 选取的核素列表

Table 2. Nuclides chosen

actinide nuclides	fission products
²³⁴U, ²³⁵U, ²³⁶U, ²³⁸U	¹⁵¹Eu, ¹⁵³Eu, ¹⁴³Nd, ¹⁴⁵Nd, ¹⁴⁸Nd
²³⁸Pu, ²³⁹Pu, ²⁴⁰Pu, ²⁴¹Pu, ²⁴²Pu	¹⁴⁷Sm, ¹⁴⁹Sm, ¹⁵⁰Sm, ¹⁵¹Sm, ¹⁵²Sm
²³⁷Np, ²⁴¹Am, ²⁴³Am, ²⁴⁴Cm	¹⁵⁵Gd

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