带蛇的整体式小型熔盐堆耗损计算

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-08-05 DOI:10.1115/1.4063111
Xiaolin Wang, T. S. Nguyen, D. Wojtaszek
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引用次数: 0

摘要

熔盐堆(MSR)概念是第四代设计之一,被认为可以为世界人口提供清洁、安全、可持续和经济的能源供应。采用Serpent对基于整体式熔盐堆(IMSR)概念的密闭燃料循环的小型模块化氟化熔盐堆(sm-FMSR)的燃料耗尽进行了研究。模拟和比较了控制Serpent耗尽循环的三种燃料方案:分步燃料(SF)、所有裂变产物(FPs)积聚在反应堆系统中的连续燃料(CFA)和不溶性裂变产物与燃料分离的连续燃料(CFS)。使用SF和CFA的sm - fmsr需要相似数量的“补充”燃料,消耗相似的燃料(裂变)量,并且如果keff保持在相似的范围内,则产生相似的燃料同位素浓度。然而,随着不溶性FP从循环燃料中分离出来,CFS由于去除FP毒素而获得了很大的反应性价值。这允许减少初始和总补充燃料中的燃料浓缩,并导致在为MSR和乏燃料提供燃料时节省相当大的裂变量。在所有三种加油方案的每个计算周期开始之前,毒蛇耗尽计算需要手动计算来调整毒蛇内置设置。在改变材料体积和流动常数方面实施额外的蛇形流动特征将有助于模拟燃料耗尽过程,并允许更真实地模拟燃料循环。
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Depletion Calculations For An Integral Small Molten Salt Reactor With Serpent
The molten salt reactor (MSR) concept is among the Generation IV designs considered feasible for providing clean, safe, sustainable, and economical energy supplies to the world's population. The depletion of fuel for a small modular fluoride molten salt reactor (sm-FMSR) with a closed fuel cycle based on the integral molten salt reactor (IMSR) concept has been investigated using Serpent. Three fueling schemes to control Serpent depletion cycles have been simulated and compared: step fueling (SF), continuous fueling with all fission products (FPs) accumulating in the reactor system (CFA), and continuous fueling with insoluble FPs separated from fuel (CFS). Sm-FMSRs with SF and with CFA require similar quantities of "top-up" fuel, consume similar fuel (fissile) amounts, and result in similar fuel isotopic concentrations if keff is kept within a similar range. However, with separation of insoluble FPs from the circulating fuel, CFS gains a large reactivity worth due to the removal of FP poisons. This allows for reduction of fuel enrichment in both initial and total top-up fuel, and leads to savings of a considerable fissile quantity in fueling MSR and in spent fuel. The Serpent depletion calculations require manual arithmetic calculations for adjustment of the Serpent built-in settings before the start of every calculation cycle for all three fueling schemes. Implementation of additional Serpent flow features in changing material volumes and flow constants would facilitate the simulation of the fuel depletion process and allow for more realistic simulations of fuel circulation.
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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.
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