NUCLEAR TECHNIQUES, Volume. 46, Issue 7, 070605(2023)
Influence of thermal neutron scattering effect of FLiBe molten salt on neutronic performance of molten salt reactors
Figures & Tables(11)
Fig. 1. Structural diagram of calculation model for the reactor core
Fig. 2. Influence of FLiBe thermal scattering on the neutron spectrum
Fig. 3. Influence of FLiBe thermal scattering on the neutron spectrum in the ranges of 0.05⁓0.08 eV (a) and 0.2⁓0.4 eV (b)
Fig. 5. Variation of the core energy spectrum with the molten salt volume fraction
Fig. 6. Variation of the reaction rate with the volume fraction of molten salt
Fig. 7. Influence of thermal scattering on keff as a function of the volume fraction
Table 1. Main parameters of the reactor core
View tableView in ArticleTable 1. Main parameters of the reactor core
主要参数 Main paramenters 数值 Values 燃料盐成分 Composition of fuel salt / mol% 65.31%LiF-28.67%BeF2-4.78%ZrF4-1.24%UF4 熔盐密度（900 K）Density of fuel salt (900 K) / g∙cm-3 2.311 7Li丰度 7Li abundance / % 99.95 235U富集度 235U enrichment / % 19.75 石墨密度 The density of graphite / g∙cm-3 1.785 活性区高度/直径 Height/diameter of active region / cm 252/252 燃料通道半径 Radius of fuel channel / cm 3 石墨组件对边距 Graphite assembly pitch / cm 14
Table 2. Changes in neutron activity in the MSR
View tableView in ArticleTable 2. Changes in neutron activity in the MSR
反应道
Neutron activities
自由气体模型计算结果
Calculation result of free gas
model / collisions·cm-3·s-1
热中子散射计算结果
Calculation result of TSL
/ collisions·cm-3·s-1
差值
Difference
/ 10-5 collisions·cm-3·s-1
235U俘获 235U capture rate 0.107 70 0.107 75 5 238U俘获 238U capture rate 0.076 92 0.076 93 1 熔盐吸收 Molten salt absorption rate 0.150 39 0.150 40 1 235U裂变 235U fission rate 0.522 68 0.522 29 -39 238U裂变 238U fission rate 0.000 57 0.000 57 0
Table 3. Fitted results for the fuel temperature reactivity coefficient
View tableView in ArticleTable 3. Fitted results for the fuel temperature reactivity coefficient
自由气体模型计算结果
Calculation result of free gas
model / 10-5 K-1
热中子散射计算结果
Calculation result of TSL
/ 10-5 K-1
差值
Difference
/ 10-5 K-1
密度系数 Density coefficient -0.97 -0.99 -0.02 多普勒系数 Doppler coefficient -3.23 -3.52 -0.28 燃料总温度系数 Fuel temperature coefficient -4.25 -4.50 -0.25
Table 4. Effect of FLiBe thermal neutron scattering on keff
View tableView in ArticleTable 4. Effect of FLiBe thermal neutron scattering on keff
体积份额
Volume fraction / %
自由气体模型
Free gas model
热中子散射
TSL
差值
Difference / 10-5
16.6 1.245 95(0.000 05) 1.245 03(0.000 05) -92 20.4 1.217 62(0.000 05) 1.216 87(0.000 05) -75 24.9 1.185 86(0.000 05) 1.185 18(0.000 05) -68 30.6 1.143 35(0.000 05) 1.142 79(0.000 05) -56 35.7 1.099 65(0.000 05) 1.099 30(0.000 05) -35 45.7 1.026 62(0.000 05) 1.026 42(0.000 05) -20
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Zhicheng ZHANG, Jifeng HU, Jingen CHEN, Xiangzhou CAI. Influence of thermal neutron scattering effect of FLiBe molten salt on neutronic performance of molten salt reactors[J]. NUCLEAR TECHNIQUES, 2023, 46(7): 070605
Paper Information
Category: Research Articles
Received: Apr. 4, 2023
Accepted: --
Published Online: Aug. 3, 2023
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