具有固定容积的单流体熔盐反应堆(OFMSR)的验证和几何优化

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Engineering and Radiation Science Pub Date : 2024-01-10 DOI:10.1115/1.4064465
R. A. P. Dwijayanto, Harun Ardiansyah, A. W. Harto
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引用次数: 0

摘要

热熔盐反应堆可以设计成多种配置。本文研究了一流体熔盐反应堆(OFMSR)在固定燃料盐体积的虚拟一流体半配置下的最佳几何形状。研究了两种主要配置:轴向毯式(三个模型)和径向毯式(两个模型)。中子计算使用 MCNP6.2 和 Serpent-2 反应堆物理代码以及 ENDF/B-VII.0 连续中子库进行。分析包括临界计算、反应温度系数(TCR)、繁殖比(BR)和动力学参数。结果表明 MCNP 和 Serpent 的计算结果非常吻合。轴向和径向橡皮布配置的 TCR 值显示出不同的模式。在轴向毯状结构中,TCR 与 BR 之间的相关性呈反比,而在径向毯状结构中则呈线性。总体而言,径向毯配置似乎比轴向毯配置显示出更好的中子性能,具有相当强的负 TCR 和较大的 BR。
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Verification and Geometry Optimization of a One Fluid Molten Salt Reactor (OFMSR) with Fixed Volume
Thermal molten salt reactors can be designed in many configurations. This paper investigates the optimal geometry of a one fluid molten salt reactor (OFMSR) in a virtual one-and-half fluid configuration with a fixed fuel salt volume. Two primary configurations were studied, axial blanket (three models) and radial blanket (two models). Neutronic calculations were performed using MCNP6.2 and Serpent-2 reactor physics codes with ENDF/B-VII.0 continuous neutron library. The analysis comprises criticality calculation, temperature coefficient of reactivity (TCR), breeding ratio (BR), and kinetic parameters. The results imply a good agreement between MCNP and Serpent calculations. TCR values show a different pattern between axial and radial blanket configuration. Whilst the correlation between TCR and BR is inversely correlated in axial blanket, it is linear in radial blanket configuration. Overall, radial blanket configuration seemed to show better neutronic performance than axial blanket configuration, with comparably strong negative TCR and large BR.
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
期刊最新文献
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