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
Influence of different types of nuclear fuel on burnup performance of heat pipe cooled reactor
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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，(U0.9Pu0.1)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。
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关键词:
- 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, (U0.9Pu0.1)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.-
Key words:
- heat pipe cooled reactor /
- burnup calculation /
- RMC code /
- 241Pu nuclide
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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keff随燃耗深度的变化
Figure 2. Core keff of different nuclear fuel varies with burnup depth
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图 3 堆芯keff随控制鼓旋转的变化
Figure 3. Core keff 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keff计算结果
Table 1. Calculation results of effective increment coefficient keff
control condition calculated value of keff in this paper calculated value of keff of INL difference of keff /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 at 5 MW at 200 MW 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 at 5 MW at 200 MW 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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