铅冷行波堆反应性变化规律及其影响因素研究

秦天骄; 夏榜样; 李晴; 李司南; 张策; 卢迪

doi:10.13832/j.jnpe.2022.04.0206

铅冷行波堆反应性变化规律及其影响因素研究

doi: 10.13832/j.jnpe.2022.04.0206

中国核动力研究设计院核反应堆系统设计技术重点实验室，成都，610213

详细信息

作者简介:
秦天骄（1997—），男，硕士研究生，现从事反应堆物理研究，E-mail: qintianjiao@yeah.net

中图分类号: TL425
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出版历程
- 收稿日期: 2022-03-31
- 修回日期: 2022-05-13
- 网络出版日期: 2022-08-12
- 刊出日期: 2022-08-04

Study on Reactivity Variation and Its Influencing Factors of Lead-cooled Traveling Wave Reactor

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

摘要

摘要: 铅冷行波堆具有安全性好、倒换料周期长、铀资源利用率高等突出优势，是先进核能系统的重点发展方向之一，实现反应性微小变化是铅冷行波堆堆芯方案设计的关键技术问题。本文以热功率700 MW、采用金属燃料的铅冷行波堆物理方案为研究对象，重点研究了堆芯点火区及增殖区设计参数变化对有效增殖因子（k_eff）的影响，分析了全寿期堆芯反应性的变化趋势。数值结果表明：点火区设计参数显著影响堆芯初始k_eff，点火区的易裂变核素装量越大，初始k_eff越大，通过调整点火区在堆芯轴向位置及其燃料富集度可有效降低反应性变化幅度；堆芯装载的可转换核素与易裂变核素之比越高，增殖产生的²³⁹Pu越多，整体增殖性能越好；增殖区越长，平衡态持续时间越长，堆芯寿期越长。本文研究结论可为铅冷行波堆堆芯物理方案设计及关键参数选择提供重要理论依据。
- 铅冷行波堆 /
- 有效增殖因子（k_eff） /
- 点火区 /
- 增殖区
Abstract: Lead-cooled traveling wave reactor has outstanding advantages of good safety, long refueling and shuffling cycles, and high utilization rate of uranium resources. It is one of the key development directions of advanced nuclear energy system. Realizing the small change of reactivity is the key technical problem in the core scheme design of lead-cooled traveling wave reactor. Taking the physical scheme of lead-cooled traveling wave reactor with thermal power of 700MW and metal fuel as the research object, this paper focuses on the influence of the design parameters of core ignition zone and breeder zone on the effective multiplication factor (k_eff), and analyzes the change trend of core reactivity in the whole life. The numerical results show that ignition zone design parameters significantly affect the initial k_effof the core. The larger the amount of fissile nuclides in the ignition zone, the larger the initial k_eff. The variation range of reactivity can be effectively reduced by adjusting the axial position of the ignition zone in the core and its fuel enrichment; The higher the ratio of convertible nuclides to fissile nuclides loaded in the core, the more ²³⁹Pu produced by breeding, and the better the overall breeding performance; The longer the breeder zone, the longer the duration of equilibrium state and the longer the core life. The conclusions of this paper can provide an important theoretical basis for the physical scheme design of lead-cooled traveling wave reactor core and the selection of key parameters.
- Lead-cooled traveling wave reactor /
- Effective multiplication factor ( k_eff) /
- Ignition zone /
- Breeder zone

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图 1 蜂窝型燃料组件

Figure 1. Honeycomb Fuel Assembly

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图 2 堆芯布置示意图

Figure 2. Schematic Diagram of Core Layout

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图 3 1/8堆芯计算模型

Figure 3. 1/8 Core Calculation Model

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图 4 不同点火区长度下堆芯k_eff随燃耗变化

Figure 4. Variation of k_eff with Burnup under Different Ignition Zone Lengths

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图 5 不同点火区长度下²³⁹Pu核子密度随燃耗变化

Figure 5. Variation of Nucleon Density of ²³⁹Pu with Burnup under Different Ignition Zone Lengths

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图 6 不同²³⁵U富集度下堆芯k_eff随燃耗变化

Figure 6. Variation of k_eff with Burnup under Different ²³⁵U Enrichment

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图 7 不同²³⁵U富集度下²³⁹Pu核子密度随燃耗变化

Figure 7. Variation of Nucleon Density of ²³⁹Pu with Burnup under Different ²³⁵U Enrichment

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图 8 不同点火区位置堆芯k_eff随燃耗的变化

Figure 8. Variation of k_eff with Burnup under Different Ignition Zone Locations

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图 9 不同点火区位置下²³⁹Pu核子密度随燃耗的变化

Figure 9. Variation of Nucleon Density of ²³⁹Pu with Burnup under Different Ignition Zone Locations

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图 10 不同增殖区长度下堆芯k_eff随燃耗变化

Figure 10. Variation of k_eff with Burnup under Different Breeder Zone Lengths

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图 11 不同增殖区长度下²³⁹Pu质量随燃耗变化

Figure 11. Variation of Mass of ²³⁹Pu with Burnup under Different Breeder Zone Lengths

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表 1 燃料组件设计参数

Table 1. Fuel Assembly Design Parameters

参数名	参数值
几何形状	正方形
冷却剂流道外径/mm	7.2
冷却剂流道内径/mm	6.2
流道中心距/mm	10.0
冷却剂流道排列	15×15
燃料组件横截面积/mm²	24649
燃料体积份额/%	54.1163
结构材料体积份额/%	14.5400
冷却剂体积份额/%	31.3437
燃料组件对边距/mm	154.0
燃料组件盒厚度/mm	2.0

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表 2 点火区金属燃料成分

Table 2. Metal Fuel Composition in Ignition Zone

核素	质量分数/%	核素	质量分数/%
²³⁵U	3.3600	²³⁸U	80.6400
²³⁸Pu	0.1596	²³⁹Pu	2.8386
²⁴⁰Pu	1.5048	²⁴¹Pu	0.9360
²⁴²Pu	0.5610	⁹¹Zr	10.0000

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表 3 HT-9不锈钢成分

Table 3. HT-9 Stainless Steel Composition

元素	质量分数/%	元素	质量分数/%
Fe	84.200	Mn	0.590
Cr	12.100	W	0.580
Ni	0.600	Si	0.390
Mo	0.920	V	0.310
Ti	0.002	C	0.171
O	0.016

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表 4 增殖区金属燃料成分

Table 4. Metal Fuel Composition in Breeder Zone

核素	质量分数/%	核素	质量分数/%
²³⁵U	0.6029	²⁴⁰Pu	0.3311
²³⁶U	0.6608	²⁴¹Pu	0.2060
²³⁸U	97.2323	²⁴²Pu	0.1235
²³⁷Np	0.0742	²⁴¹Am	0.0014
²³⁸Pu	0.0351	²⁴³Am	0.0333
²³⁹Np	0.0566	²⁴²Cm	0.0011
²³⁹Pu	0.6247	²⁴⁴Cm	0.0176

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表 5 组件材料参数

Table 5. Assembly Meterial Parameters

材料	体积份额/%	密度/（g·cm⁻³）	平均温度/K	质量分数/%
核燃料	54.12	14	1000	63.55
结构材料	14.54	7.37	1000	08.99
冷却剂	31.34	10.44	700	27.46

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表 6 不同点火区长度堆芯寿期末²³⁸U和²³⁹Pu变化

Table 6. Variation of ²³⁸U and ²³⁹Pu at the End of Life of Core under Different Ignition Zone Lengths

点火区长度/cm	40	60	80
²³⁸U利用率/%	32.50	32.06	31.66
²³⁹Pu产生量/kg	370.3	353.2	337.6
²³⁹Pu产生率/%	479.3	373.7	301.9

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表 7 不同²³⁵U富集度下堆芯寿期末²³⁸U和²³⁹Pu变化

Table 7. Variation of ²³⁸U and ²³⁹Pu at the End of Life of Core under Different ²³⁵U Enrichment

²³⁵U富集度/%	5	6	7
²³⁸U利用率/%	32.5	32.3	32.1
²³⁹Pu产生量/kg	370.3	368.6	367.7
²³⁹Pu产生率/%	479.3	477.2	476

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表 8 不同点火区位置堆芯寿期末²³⁸U和²³⁹Pu变化

Table 8. Variation of ²³⁸U and ²³⁹Pu at the End of Life of Core under Different Ignition Zone Locations

方案	40/160	20/40/140	40/40/120
²³⁸U利用率/%	34.6	34.7	34.8
²³⁹Pu产生量/kg	354.3	360.6	367.4
²³⁹Pu产生率/%	358.6	365	371.8

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表 9 不同增殖区长度堆芯寿期末²³⁸U和²³⁹Pu变化

Table 9. Variation of ²³⁸U and ²³⁹Pu at the End of Life of Core under Different Breeder Zone Lengths

增殖区长度/cm	120	140	160
²³⁸U利用率/%	38	34.7	31.7
²³⁹Pu产生量/kg	319.8	360.6	381.2
²³⁹Pu产生率/%	338.2	365	369.8

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参考文献(11)

[1]	HEJZLAR P. Traveling wave reactor (TWR^®)[M]. GREENSPAN E. Encyclopedia of Nuclear Energy. Amsterdam: Elsevier, 2021: 643-656.
[2]	FEINBERG S M, KUNEGIN E P. Discussion comment[C]//Record of Proceedings Session B-10, International Conference on the Peaceful Uses for Atomic Energy. Geneva, Switzerland: United Nations, 1958: 447.
[3]	郑美银,陈平,张大林,等. 钠冷驻波堆堆芯概念设计研究[J]. 核动力工程,2018, 39(S1): 79-83.
[4]	严明宇,陈彬,冯琳娜,等. 行波堆堆芯设计初步研究[J]. 核动力工程,2015, 36(4): 32-36.
[5]	SEKIMOTO H, RYU K, YOSHIMURA Y. CANDLE: the new burnup strategy[J]. Nuclear Science and Engineering, 2001, 139(3): 306-317. doi: 10.13182/NSE01-01
[6]	ELLIS T, PETROSKI R, HEJZLAR P, et al. Traveling-wave reactors: a truly sustainable and full-scale resource for global energy needs[C]//Proceedings of the International Congress on Advances in Nuclear Power Plants. San Diego, CA, USA, 2010.
[7]	SEKIMOTO H, NAGATA A. "CANDLE" burnup regime after LWR regime[J]. Progress in Nuclear Energy, 2008, 50(2-6): 109-113. doi: 10.1016/j.pnucene.2007.10.012
[8]	WANG K, LI Z G, SHE D, el al. RMC – A Monte Carlo code for reactor core analysis[J]. Annals of Nuclear Energy, 2015, 82: 121-129. doi: 10.1016/j.anucene.2014.08.048
[9]	SIENICKI J J, MOISSEYTSEV A, YANG W S, et al. Status report on the small secure transportable autonomous reactor (SSTAR)/lead-cooled fast reactor (LFR) and supporting research and development: ANL-GenIV-089[R]. Argonne: Argonne National Lab, 2008.
[10]	YU R, SEMENOV M. BFS-61 assemblies: critical experiments of mixed plutonium, depleted uranium, graphite and lead with different reflectors: NEA/NS/DOC(2006)[R]. Idaho: Idaho National Laboratory, 2013.
[11]	孙伟. 行波堆物理分析方法及物理特性研究[D]. 北京: 清华大学, 2014.