热管堆在不同基体材料下的燃耗特性分析

马坤峰; 胡珀

doi:10.11884/HPLPB202234.210388

热管堆在不同基体材料下的燃耗特性分析

doi: 10.11884/HPLPB202234.210388

马坤峰,
胡珀^,

上海交通大学核科学与工程学院, 上海 200240

基金项目: 国家自然科学基金项目(11205098)

详细信息

作者简介:
马坤峰，2456230687@sjtu.edu.cn

通讯作者:
胡　珀，pohu@sjtu.edu.cn

中图分类号: TL327
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- 文章访问数: 1038
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- PDF下载量: 60
- 被引次数: 0
出版历程
- 收稿日期: 2021-08-31
- 修回日期: 2021-10-29
- 录用日期: 2021-11-08
- 网络出版日期: 2021-11-15
- 刊出日期: 2022-01-11

Depletion calculation of heat pipe cooled nuclear reactor with different monolithic materials

Ma Kunfeng,
Hu Po^,

School of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai 200240, China

摘要

摘要: 热管冷却核反应堆具有非能动传热、模块化和固有安全性高等特点，在航空探索、深海作业和偏远地区电力市场上有广泛的应用。以洛斯阿拉莫斯国家实验室开发的5 MW_th热管堆为研究对象，选择SS-316，Mo-14Re和SiC作为基体候选材料，采用反应堆蒙特卡罗中子输运分析程序对比分析了以上三种基体堆芯的反应性、中子能谱、增殖性能和燃耗演化。结果表明：为了维持堆芯的10年运行，SS-316，Mo-14Re和SiC三种基体堆芯所需的初始燃料²³⁵U富集度分别约为19.35%，28.80%和17.10%，SiC基体堆芯所需的初始燃料²³⁵U富集度最小；10年后，SiC基体堆芯产生的易裂变核素（²³⁹Pu和²⁴¹Pu）和次锕系核素（通过分离嬗变可被再次利用）的量最高，分别约为11.91 kg和92.08 g。综合以上研究结果，推荐SiC作为热管冷却核反应堆的基体。
- 反应堆蒙特卡罗程序 /
- 热管堆 /
- 基体 /
- SS-316 /
- Mo-14Re /
- SiC
Abstract: Heat pipe cooled nuclear reactor has unique advantages, such as passive heat transfer technology, modular design and inherent safety. It has been extensively used in deep space, deep sea and decentralized electricity markets. Recently, Los Alamos National Laboratory designed a 5 MW_th heat pipe cooled nuclear reactor for decentralized electricity markets. This paper aimed to provide an appropriate reference for the choice of types of monolithic core in the engineering design of heat pipe cooled nuclear reactor. With the help of a Monte Carlo simulation program RMC, reactivity, neutron spectrum, breeding performance and burnup evolution were explored on the heat pipe cooled nuclear reactor with monolith materials SS-316, SiC and Mo-14Re, respectively. The results show the reactor with monolith materials SS-316, Mo-14Re and SiC can achieve a 10-year operation when the enrichment of the initially loaded ²³⁵U is about 19.35%, 28.80% and 17.10%, respectively. The SiC monolith core requires the least initial ²³⁵U enrichment. Besides, the core with SiC monolith can produce the highest mass of fissile ²³⁹Pu and ²⁴¹Pu (about 11.91 kg) and minor actinides (about 92.08 g) for a 10-year operation. Thus, SiC monolith is recommended for the pipe cooled nuclear reactor.
- Reactor Monte Carlo Code /
- heat pipe reactor /
- monolith /
- SS-316 /
- Mo-14Re /
- SiC

HTML全文

图 1 RMC的堆芯几何模型

Figure 1. RMC model of heat pipe cooled nuclear reactor

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图 2 不同基体材料下堆芯的k_eff随时间变化

Figure 2. Evolution of k_eff for reactor with different monolithic materials

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图 3 三种基体堆芯初装²³⁵U富集度、²³⁵U和²³⁸U质量

Figure 3. Loaded ²³⁵U enrichment, ²³⁵U and ²³⁸U mass for reactor with different monolithic materials

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图 4 初始时刻3种基体堆芯的中子能谱

Figure 4. Initial neutron spectrum of core with different monolithic materials

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图 5 3种基体堆芯内²³⁹Pu的量随时间的演变

Figure 5. Inventory of ²³⁹Pu in three monolithic material cores

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图 6 三种基体堆芯内²⁴¹Pu的量随时间的演变

Figure 6. Inventory of ²⁴¹Pu in three monolithic materials core

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图 7 ²⁴¹Pu的中子俘获截面和裂变截面

Figure 7. Neutron capture cross and fission cross of ²⁴¹Pu

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图 8 3种基体堆芯内²³⁷Np的量随时间的演变

Figure 8. Inventory of ²³⁷Np in three monolithic material cores

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图 9 3种基体堆芯内²⁴¹Am的量随时间的演变

Figure 9. Inventory of ²⁴¹Am in three monolithic material cores

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