Abstract This study highlights Integral Molten Salt Reactors and models a beginning-of-life Integral (core assembly and primary loop components inside the core vessel) Molten Salt Reactor (MSR) in Monte Carlo N-Particle (MCNP) particle transport code and compares fundamental neutronic and thermal performance characteristics against known MSRs such as the ORNL MSRE and FUJI-MSR. Evaluations of core fast and thermal neutron flux, basic thermal performance, and core lifetime will be compared to known performance benchmarks. This study utilizes the Idaho National Laboratory (INL) High Performance Computing (HPC) facility, including the Falcon 2 SGI ICE-X distributed memory system with 34,992 cores to complete the necessary computations. This study will inform follow-on work on the IMSR molten salt and fuel cycle alternatives. Conceptual designs evaluated in this study preserve the inherent safety and economic benefits associated with proliferation risk and safeguards in reactor control, cooling, and containment. Recommendations for further study include conducting fuel burnup analysis using Serpent code, completing a parametric analysis on fuel cycle performance, and coupling INL’s MOOSE object oriented applications to predict steady state and time-dependent neutronics, thermal-fluids, and fuel material performance in MSRs.

中文翻译：

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使用蒙特卡罗 N 粒子代码进行整体熔盐反应堆中子物理研究

摘要 本研究重点介绍了整体熔盐反应器，并在蒙特卡洛 N 粒子 (MCNP) 粒子传输代码中模拟了生命开始的整体（核心组件和核心容器内的主要回路组件）熔盐反应器 (MSR)，并比较了基本的与已知 MSR（如 ORNL MSRE 和 FUJI-MSR）相比的中子和热性能特征。对堆芯快中子通量和热中子通量、基本热性能和堆芯寿命的评估将与已知的性能基准进行比较。本研究利用爱达荷州国家实验室 (INL) 高性能计算 (HPC) 设施，包括具有 34,992 个内核的 Falcon 2 SGI ICE-X 分布式内存系统来完成必要的计算。这项研究将为 IMSR 熔盐和燃料循环替代品的后续工作提供信息。本研究中评估的概念设计保留了与反应堆控制、冷却和安全壳方面的扩散风险和保障措施相关的固有安全性和经济效益。进一步研究的建议包括使用 Serpent 代码进行燃料燃烧分析，完成对燃料循环性能的参数分析，以及结合 INL 的 MOOSE 面向对象应用程序来预测 MSR 中的稳态和瞬态中子学、热流体和燃料材料性能。