Design and optimization of the components of a molten salt, thorium-fueled accelerator driven system

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Progress in Nuclear Energy Pub Date : 2024-10-15 DOI:10.1016/j.pnucene.2024.105486

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Abstract

Molten Salt Accelerator-Driven Systems (MoSTADS) have been attracting a lot of research interest lately due to their unique characteristics and advantages, including reduced radiation damage of the fuel, and stable operation achieved through online fuel feeding process. Simulations of an experimental molten salt test facility being developed in the Thermal Hydraulic Research Laboratory (THRL) at Texas A&M University, were conducted using Monte Carlo radiation transport methods, to design and optimize selected components of the system. The system consists of a proton beam generated by an accelerator, impinging on a target to generate neutrons, which can be used induce fission reactions within a thorium fueled, high-temperature molten salt forced convection test loop. Parametric studies were performed to optimize several key components of the system including target material, proton beam energy, target thickness and location, and reflector thickness. Furthermore, in order to ensure the safe operation of the facility, parametric studies were also performed to identify the composition and thickness of the system shielding that would be needed to satisfy acceptable exposure limits.

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熔盐钍燃料加速器驱动系统组件的设计与优化

熔盐加速器驱动系统（MoSTADS）因其独特的特性和优势，包括减少燃料的辐射损伤以及通过在线燃料供给过程实现稳定运行等，近来吸引了大量研究人员的关注。德克萨斯A&M大学热液压研究实验室（THRL）正在开发一种实验性熔盐试验设备，我们采用蒙特卡洛辐射传输方法对该设备进行了模拟，以设计和优化系统的选定组件。该系统由加速器产生的质子束组成，质子束撞击目标产生中子，中子可用于诱导以钍为燃料的高温熔盐强制对流试验回路中的裂变反应。参数研究旨在优化系统的几个关键组件，包括靶材料、质子束能量、靶厚度和位置以及反射器厚度。此外，为了确保设施的安全运行，还进行了参数研究，以确定满足可接受的暴露限值所需的系统屏蔽成分和厚度。

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来源期刊

Progress in Nuclear Energy 工程技术-核科学技术

CiteScore

5.30

自引率

14.80%

发文量

331

审稿时长

3.5 months

期刊介绍： Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.