熔盐快堆Th-U燃料循环增殖性能分析

doi:10.11889/j.0253-3219.2020.hjs.43.050604

Nuclear Techniques ›› 2020, Vol. 43 ›› Issue (5): 50604-050604.doi: 10.11889/j.0253-3219.2020.hjs.43.050604

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles Next Articles

Analysis of Th-U breeding in molten salt fast reactor

Dongguo LIU Guimin LI

Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China

Received:2019-11-26 Revised:2020-03-10 Online:2020-05-15 Published:2020-05-07
Supported by:
Strategic Priority Research Program of Chinese Academy of Sciences(XDA02010000);Frontier Science Key Program of Chinese Academy of Sciences(QYZDY-SSW-JSC016)

Abstract

Abstract: Background

Because of its superior performance, molten salt reactor has been selected as one of the candidates for the fourth-generation reactors, and has become the focus of international attention.

Purpose

In the molten salt fast neutron reactor, we try to find the most suitable molten salt fuel scheme to achieve the purpose of high proliferation of fissile nuclides.

Methods

Based on the two-fluid cooling cycle scheme, independent cooling cycles of fission molten salt fuel and breeding molten salt, a comprehensive simulation program SCALE (Standardized Computer Analyses for Licensing Evaluation) was employed to achieve high breeding ratio (BR) in the molten salt fast reactor by utilizing the high solubility characteristics of thorium and uranium heavy metal salts in fluorinated or chlorinated molten salts at high temperatures. Three feasible molten salt fuel schemes (LiF+ThF₄+UF₄, NaF+ThF₄+UF₄, and NaCl+ThCl₃+UCl₃) were compared by calculating the neutron energy spectrum and the reactivity temperature coefficient. Influence factors of BR, such as the sizes of fission zone, breeding zone and ZrC reflective layer, the isotopic abundance of ⁶Li and ³⁵Cl in the molten salt, molten salt density error on the calculation accuracy, and the evolution of fissile nuclides with reactor operating time, were computationally analyzed.

Results

The breeding ratio (BR) of reactor reaches about 1.2 in all three molten salt fuel schemes when the diameter and height of the fission zone are both 260 cm.

Conclusions

With optimization of the reactor geometry, and the composition and isotopic abundance of the molten salt fuel, a high breeding ratio of the reactor is achievable for the thorium-uranium fuel cycle of molten salt fast reactor.

Key words: Molten salt reactor, Fast neutron reactor, Breeder, Neutron physics, Thorium-uranium cycle, Breeding ratio

CLC Number:

Dongguo LIU Guimin LI. Analysis of Th-U breeding in molten salt fast reactor[J].Nuclear Techniques, 2020, 43(5): 50604-050604.

Figures/Tables 15

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	LiF+ThF₄	NaF+ThF₄	NaCl+ThCl₃
平均温度Average temperature / ℃	700	800	700
重金属摩尔浓度Heavy metal molar concentration / %	30.2	33.3	43.0
熔盐密度Molten salt density / g?cm^-3	4.568	4.140	3.380
热膨胀系数Thermal expansion coefficient / g?(cm³?K)^-1	-9.52×10^-4	-1.02×10^-3	-9.13×10^-4

几何参数 Geometry / cm	LiF+ThF₄ NaF+ThF₄	NaCl+ThCl₃
裂变区直径Fission zone diameter	260 260 20 40 1 5 30 3 20 418 418	260
裂变区高度Fission zone height 半椭球高度Height of half ellipsoid		260 20
增殖区厚度Breeding zone thickness		70
隔离层厚度Isolation layer thickness		1
反射层厚度Reflective layer thickness		5
吸收层厚度Absorptive layer thickness		30
外壳厚度Shell thickness		3
进出口半径Import and export radius		20
堆本体直径Reactor diameter		478
堆本体高度Reactor height		478

	LiF+ThF₄	NaF+ThF₄	NaCl+ThCl₃
裂变熔盐成分Fission molten salt composition	LiF+ThF₄+UF₄	NaF+ThF₄+UF₄	NaCl+ThCl₃+UCl₃
临界状态Critical state	69.8%+27.075%+3.125%	66.7%+29.754%+3.546%	57%+37.785%+5.215%
满功率状态Full power state	69.8%+26.941%+3.259%	66.7%+29.60%+3.70%	57%+37.533%+5.467%
增殖熔盐Breeding molten salt	LiF+ThF₄=69.8%+30.2%	NaF+ThF₄=66.7%+33.3%	NaCl+ThCl₃=57%+43%
⁶Li/³⁵Cl丰度 ⁶Li/³⁵Cl abundance / %	0.01	—	1
温度反应性系数 Temperature reactivity coefficient / K^-1	-6.64×10^-5	-6.73×10^-5	-11.95×10^-5
临界增殖比Critical breeding ratio	1.225	1.210	1.218
输出功率Output power / MW_th	2 368	2 014	2 442
平均功率密度Average power density / MW?m^-3	86.4	73.5	56.7
重金属装载Heavy metal loading / T	78.94	67.14	81.39
吨功率Output power / heavy metal / MW?TU^-1	20	20	20
运行时间Running time / d	2 305	1 455	205
²³²Th利用率 ²³²Th utilization / %	5.90	3.79	0.51
倍增时间Td Doubling time Td / a	169.3	185.3	No

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Analysis of Th-U breeding in molten salt fast reactor

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