不同类型核燃料对热管冷却反应堆燃耗性能的影响

秦凯文; 杨波; 王子鸣; 钱云琛; 刘豪杰; 刘义保

doi:10.11884/HPLPB202234.220156

不同类型核燃料对热管冷却反应堆燃耗性能的影响

doi: 10.11884/HPLPB202234.220156

秦凯文^1,,
杨波^{1, 2, ,},
王子鸣¹,
钱云琛¹,
刘豪杰¹,
刘义保^{1, 2, ,}

1.
东华理工大学核科学与工程学院，南昌 330013
2.
东华理工大学核资源与环境国家重点实验室，南昌 330013

基金项目: 国家自然科学基金项目(11965001); 江西省教育厅科技计划重点项目(GJJ170428); 江西省自然科学基金项目(20212BAB201004)

详细信息

作者简介:
秦凯文，2549820280@qq.com

通讯作者:
杨　波，Boyang@ecut.edu.cn

刘义保，ybliu@ecut.edu.cn

中图分类号: TL32
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- 被引次数: 0
出版历程
- 收稿日期: 2022-05-16
- 修回日期: 2022-09-26
- 网络出版日期: 2022-11-02
- 刊出日期: 2022-11-02

Influence of different types of nuclear fuel on burnup performance of heat pipe cooled reactor

Qin Kaiwen^1
,,
Yang Bo^{1, 2
, ,},
Wang Ziming¹,
Qian Yunchen¹,
Liu Haojie¹,
Liu Yibao^{1, 2
, ,}

1.
Nuclear Science and Technology, East China University of Technology, Nanchang 330013, China
2.
National Key Laboratory of Nuclear Resources and Environment, East China University of Technology, Nanchang 330013, China

摘要

摘要: 热管冷却反应堆采用固态反应堆设计理念，具有功率密度高、结构紧凑、固有安全性高等特点，在深空探索、深海勘探、偏远地区等场景中具有广阔的应用前景。核燃料作为热管冷却反应堆的重要组成部分，不同类型核燃料在堆芯燃耗分析时会呈现不同的中子学性能。基于美国爱达荷国家实验室(INL)提出的热管冷却反应堆INL Design A，利用清华大学蒙特卡罗中子输运程序RMC (Reactor Monte Carlo code)建立堆芯物理模型，选取UO₂，(U_0.9Pu_0.1)O₂，U-10Zr，U-8Pu-10Zr，UN，UC这6种核燃料开展燃耗计算，分析了不同核燃料、不同功率水平对热管冷却反应堆堆芯燃耗性能的影响。计算结果表明：在堆芯燃耗深度相同情况下(20.8 GW·d·t⁻¹)，装载U-8Pu-10Zr燃料的堆芯所需²³⁵U富集度最低(9.8%)，具有较好的U-Pu增殖性能。堆芯功率处于5 MW的热管冷却反应堆，燃料中²⁴¹Pu的存在不仅没起到增大堆芯燃耗深度的作用，反而导致堆芯剩余反应性和堆芯寿期末次锕系核素(MAs)的产量增大，影响反应堆的安全性与经济性。因此，对于装载含有Pu燃料的小功率长寿期热管冷却反应堆，需重点关注²⁴¹Pu对堆芯燃耗性能的影响。
- 热管冷却反应堆 /
- 燃耗计算 /
- RMC程序 /
- ²⁴¹Pu核素
Abstract: The heat pipe cooled reactor adopts the solid-state reactor design concept, and it has the characteristics of high power density, compact structure and high inherent safety. It has been extensively used for deep space exploration, deep sea exploration, remote areas electricity markets and other scenarios. Nuclear fuel is an important part of the heat pipe cooling reactor, different types of nuclear fuel will reflect different neutronics performance on the reactor burnup analysis. In this paper, based on the heat pipe cooled reactor INL Design A proposed by the Idaho National Laboratory (INL), the burnup calculation is done by selecting six nuclear fuels : UO₂, (U_0.9Pu_0.1)O₂, U-10Zr, U-8Pu-10Zr, UN and UC. The effects of different nuclear fuel and power levels on the burnup performance of heat pipe cooled reactor core were analyzed. The calculation results show that under the same core burnup depth (20.8 GW·d·t⁻¹), the core loaded with U-8Pu-10Zr fuel requires the lowest ²³⁵U enrichment (9.8%), and has better U-Pu breeding. For the heat pipe cooling reactor with the core power of 5 MW, the presence of ²⁴¹Pu in the fuel does not increase the core burnup depth, but leads to the increase of residual reactivity of the core and the yield of the secondary actinides nuclides (MAs) in the core end of life, which affects the safety and economy of the reactor. Therefore, for the low-power and long-life heat pipe cooled reactor loaded with Pu fuel, it is necessary to focus on the influence of ²⁴¹Pu on the core burnup performance.
- heat pipe cooled reactor /
- burnup calculation /
- RMC code /
- ²⁴¹Pu nuclide

HTML全文

图 1 RMC输出INL Design A几何结构图

Figure 1. Geometries of INL Design A by RMC

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图 2 不同核燃料堆芯k_eff随燃耗深度的变化

Figure 2. Core k_eff of different nuclear fuel varies with burnup depth

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图 3 堆芯k_eff随控制鼓旋转的变化

Figure 3. Core k_eff change with rotation of control drum

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图 4 不同功率反应堆堆芯燃耗

Figure 4. Reactor core burnup of different power

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图 5 不同功率下不含²⁴¹Pu反应堆堆芯燃耗

Figure 5. Reactor core burnup without ²⁴¹Pu at different powers

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图 6 U-Pu燃料循环燃耗链

Figure 6. Burnup chain of U-Pu cycle

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表 1 有效增值系数k_eff计算结果

Table 1. Calculation results of effective increment coefficient k_eff

control condition	calculated value of k_eff in this paper	calculated value of k_eff of INL	difference of k_eff /10⁻⁵
all poisons out	1.028 82±0.000 33	1.028 25	57
control drums rotation 180°	0.950 98±0.000 33	0.950 42	56
annular shutdown rod in	0.945 89±0.000 33	0.945 55	34
solid shutdown in	0.959 30±0.000 34	0.959 33	−3
all poisons in	0.845 04±0.000 33	0.845 94	−90

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表 2 典型压水堆乏燃料中钚的含量

Table 2. Plutonium composition in a typical PWR spent fuel

plutonium isotope	mass fraction/%
²³⁸Pu	2.332
²³⁹Pu	56.873
²⁴⁰Pu	26.997
²⁴¹Pu	6.105
²⁴²Pu	7.693

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表 3 不同功率水平反应堆燃料Pu同位素分析

Table 3. Pu isotope analysis of reactor fuel at different power levels

nuclide	quantity of fissile nuclides and fissionable nuclides/kg		difference/kg
nuclide	at 5 MW	at 200 MW	difference/kg
²³⁸Pu	8.319	10.422	2.103
²³⁹Pu	311.710	311.134	−0.576
²⁴⁰Pu	137.792	138.676	0.884
²⁴¹Pu	3.533	29.835	26.302
²⁴²Pu	37.129	37.447	0.318

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表 4 不同功率水平反应堆乏燃料分析

Table 4. Spent fuel analysis of reactor at different power levels

spent nuclear fuel	nuclide	half-life/a	quantity of fissile nuclides and fissionable nuclides/kg		difference/kg
spent nuclear fuel	nuclide	half-life/a	at 5 MW	at 200 MW	difference/kg
MAs	²³⁷Np	2.14×10⁶	2.71	0.71	2
	²⁴¹Am	432.2	27.46	2.15	25.31
	²⁴³Am	7 380	1.80	1.72	0.08
	²⁴³Cm	8 500	3.72×10⁻⁴	0	3.72×10⁻⁴
	²⁴⁴Cm	18.1	0.08	0.14	−0.06
	²⁴⁵Cm	28.5	5.43×10⁻⁴	4.25×10⁻⁴	1.18×10⁻⁴
LLFPs	⁹⁹Tc	2.11×10⁵	2.70	2.70	0
	¹²⁹I	1.27×10⁷	0.61	0.62	−0.01
	¹³⁵Cs	2.30×10⁶	3.91	4.34	−0.43

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