液态燃料氯盐快堆最小需求燃耗分析

彭玉; 朱贵凤; 牛淼淼

doi:10.13832/j.jnpe.2022.05.0051

液态燃料氯盐快堆最小需求燃耗分析

doi: 10.13832/j.jnpe.2022.05.0051

1.
南京工程学院，南京，211167
2.
中国科学院上海应用物理研究所，上海，201800

详细信息

作者简介:
彭　玉（1990—），女，副教授，现主要从事熔盐堆物理方向的研究，E-mail: upuppeng@foxmail.com

中图分类号: TL426；TL433
计量
- 文章访问数: 373
- HTML全文浏览量: 86
- PDF下载量: 41
- 被引次数: 0
出版历程
- 收稿日期: 2021-09-24
- 修回日期: 2022-04-08
- 刊出日期: 2022-10-12

Minimum Required Burnup Analysis of Liquid-fueled Molten Chlorine Salt Fast Reactor

1.
Nanjing Institute of Technology, Nanjing, 211167, China
2.
Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China

摘要

摘要: 为探究采用增殖燃烧模式运行的液态燃料氯盐快堆的平均卸料燃耗深度，基于中子平衡分析方法，选取5种常用氯盐，提出在线清除裂变气体和难溶裂变产物方案来维持增殖燃烧运行模式，主要研究分析了氯盐的重金属密度和在线处理方案对最小需求燃耗的影响以及无限栅元模型下维持增殖燃烧模式可接受的堆芯中子损失项。分析表明68NaCl-32UCl₃和20UCl₃-80UCl₄的最小需求燃耗分别是30.47%FIMA（FIMA是指已裂变原子数与初始的总装料金属原子数之比）和10.28%FIMA；清除裂变气体和难溶裂变产物后，60NaCl-40UCl₃可接受的中子损失项从3.49%提高到10.68%。结果表明氯盐的重金属密度对最小需求燃耗有明显影响，同时清除裂变气体和难溶裂变产物能够较大提高燃料盐系统的中子经济性，以及提高增殖燃烧模式运行可接受的堆芯中子损失项。
- 氯盐快堆 /
- 中子平衡分析方法 /
- 最小需求燃耗 /
- 增殖燃烧
Abstract: In order to explore the average discharge burnup depth of liquid-fueled molten chlorine salt fast reactor operating in the breed-and-burn mode, based on the neutron balance analysis method, five common chlorine salts are selected, and the scheme of online removal of fission gas and insoluble fission products is proposed to maintain the breed-and-burn operation mode. The effects of heavy metal density of chloride salt and online treatment scheme on minimum required burnup and acceptable core neutron loss term for maintaining the breed-and-burn mode in the infinite cell model are mainly studied and analyzed. The analysis shows that the minimum required burnup of 68NaCl-32UCl₃ and 20UCl₃-80UCl₄ is 30.47% FIMA (FIMA refers to the ratio of the number of fissioned atoms to the total number of initially loaded metal atoms) and 10.28% FIMA respectively; After removing fission gas and insoluble fission products, the acceptable neutron loss term for 60NaCl-40UCl₃ is increased from 3.49% to 10.68%. The results show that the density of heavy metals in chloride salts has a significant impact on the minimum required burnup, and the removal of fission gases and insoluble fission products can greatly improve the neutron economy of the fuel salt system, and at the same time, improve the acceptable core neutron loss term for the breed-and-burn operation mode.
- Molten chlorine salt fast reactor /
- Neutron balance analysis method /
- Minimum required burnup /
- Breed-and-burn

HTML全文

图 1 中子平衡示意图

Figure 1. Schematic Diagram of Neutron Balance

下载: 全尺寸图片幻灯片

图 2 不同燃料盐的过剩中子数随燃耗深度的变化

Figure 2. Excess Neutron Number with Burnup for Various Fuel Salts

下载: 全尺寸图片幻灯片

图 3 60NaCl-40UCl₃无限增殖因子和过剩中子数随燃耗的变化　　　　　

Figure 3. Evolution of Infinite Multiplication Factor and Excess Neutron Number with Burnup for 60NaCl-40UCl₃

下载: 全尺寸图片幻灯片

图 4 60NaCl-40UCl₃处理前后无限增殖因子随燃耗的变化

Figure 4. Infinite Multiplication Factor with Change of Burnup for 60NaCl-40UCl₃

下载: 全尺寸图片幻灯片

图 5 60NaCl-40UCl₃在不同中子损失项下过剩中子数随燃耗的变化　　　　　　

Figure 5. Evolution of the Excess Neutron Number for 60NaCl-40UCl₃ at Various Neutron Loss Terms

下载: 全尺寸图片幻灯片

表 1 B&B模式堆型常用燃料和燃料盐的密度

Table 1. Densities of Common Nuclear Fuels and Fuel Salts for B&B Type Reactors

固态燃料类型	UN	UC	U-10Zr	U-10Mo	U
有效密度/%	85	85	75	75	75
燃料孔隙率/%	6	6	0	0	0
燃料理论密度/（g·cm⁻³）	13.59	12.58	15.80	16.70	18.53
燃料实际密度/（g·cm⁻³）	10.86	10.05	11.85	12.53	13.90
燃料重金属密度/（g·cm⁻³）	10.91	10.30	10.67	11.29	13.90
堆芯重金属密度^①/（g·cm⁻³）	5.61	5.24	6.21	6.57	8.10

液态氯盐类型	68NaCl-32UCl₃	60NaCl-40UCl₃	15NaCl-15UCl₃-70UCl₄	UCl₄	20UCl₃-80UCl₄
密度^②/（g·cm⁻³）	3.32	3.64	3.64	3.56	3.79
堆芯重金属密度/（g·cm⁻³）	0.72	0.99	2.80	2.20	2.39
注：①堆芯燃料占比取为43.7%；②燃料盐温度为900 K

下载: 导出CSV

表 2 Q=0时各方案最小需求燃耗对比

Table 2. Comparison of Minimum Required Burnup of Each Scheme when Q=0

燃料盐类型	最小需求燃耗/%FIMA
燃料盐类型	不处理	清除裂变气体	清除裂变气体和难溶裂变产物
68NaCl-32UCl₃	30.47	27.25	19.65
60NaCl-40UCl₃	19.60	19.09	15.83
UCl₄	10.51	10.45	9.61
20UCl₃-80UCl₄	10.28	10.21	9.40
15NaCl-15UCl₃-70UCl₄	11.26	11.18	10.22

下载: 导出CSV

表 3 各方案可承受的最大中子损失项和对应的最小需求燃耗

Table 3. Maximum Acceptable Neutron Loss Term and the Corresponding Minimum Required Burnup for Each Scheme

燃料盐类型	不处理		清除裂变气体和难溶裂变产物
燃料盐类型	最大中子损失项/%	最小需求燃耗/%FIMA	最大中子损失项/%	最小需求燃耗/%FIMA
68NaCl-32UCl₃	0.33	35.70	7.49	46.40
60NaCl-40UCl₃	3.49	35.30	10.68	47.06
UCl₄	12.15	32.83	18.40	46.62
20UCl₃-80UCl₄	12.30	31.29	18.72	46.22
15NaCl-15UCl₃- 70UCl₄	11.05	33.27	17.47	47.12

下载: 导出CSV

参考文献(7)

[1]	GREENSPAN E, HEIDET F. Energy sustainability and economic stability with breed and burn reactors[J]. Progress in Nuclear Energy, 2011, 53(7): 794-799. doi: 10.1016/j.pnucene.2011.05.002
[2]	HOMBOURGER B, PAUTZ A, KREPEL J, et al. On the feasibility of breed-and-burn fuel cycles in molten salt reactors: FR17[R]. Vienna: International Atomic Energy Agency, 2017.
[3]	HOMBOURGER B, KŘEPEL J, PAUTZ A. Breed-and-burn fuel cycle in molten salt reactors[J]. EPJ Nuclear Sciences & Technologies, 2019, 5: 15.
[4]	HOMBOURGER B A. Conceptual design of a sustainable waste burning molten salt reactor[Z]. Lausanne: EPFL, 2018.
[5]	KASAM A. Conceptual design of a breed & burn molten salt reactor[D]. Cambridge: University of Cambridge, 2019.
[6]	MARTIN M V, AUFIERO M, GREENSPAN E, et al. Feasibility of a breed-and-burn molten salt reactor[J]. Transactions of the American Nuclear Society, 2017, 116: 1174-1176.
[7]	HEIDET F, GREENSPAN E. Neutron balance analysis for sustainability of breed-and-burn reactors[J]. Nuclear Science and Engineering, 2012, 171(1): 13-31. doi: 10.13182/NSE10-114