Development and demonstration of a BISON–Griffin modeling framework for the design of targeted TRISO transient experiments in the Transient Reactor Test Facility

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Jacob A. Hirschhorn, Mustafa K. Jaradat, Ryan T. Sweet, Paul A. Demkowicz, Paolo Balestra, Gerhard Strydom
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Abstract

Uranium oxycarbide (UCO)-bearing tri-structural isotropic (TRISO) particle fuels are expected to be used in numerous U.S. commercial reactor applications within the next decade. In this work, we reviewed historical particle fuel transient experiments to identify gaps in TRISO fuel performance transient testing. A BISON–Griffin modeling framework was then developed to conduct preliminary TRISO transient analyses and begin to address these gaps. The framework was demonstrated using limiting-case transient conditions from a prototypic high-temperature gas-cooled reactor (HTGR). It was then applied to develop a matrix of experiments that could be performed in the Transient Reactor Test Facility (TREAT) to (1) evaluate UCO-fueled particle performance at moderate and high heat rates, (2) assess whether historical testing involving UO2-fueled particles is applicable to modern UCO-fueled particles, (3) deconvolute the impacts of temperature and heat rate on particle transient response, and (4) collect the data needed for fuel performance model validation and/or further development.
开发并演示 BISON-Griffin 建模框架,用于在瞬态反应堆试验设施中设计有针对性的 TRISO 瞬态实验
预计在未来十年内,含碳氧铀 (UCO) 的三结构各向同性(TRISO)粒子燃料将在美国众多商业反应堆中得到应用。在这项工作中,我们回顾了历史上的粒子燃料瞬态实验,以找出 TRISO 燃料性能瞬态测试方面的差距。然后开发了一个 BISON-Griffin 建模框架,用于进行初步的 TRISO 瞬态分析,并开始弥补这些不足。利用高温气冷堆(HTGR)原型的极限情况瞬态条件对该框架进行了演示。然后将其应用于开发可在瞬态反应堆试验设施(TREAT)中执行的实验矩阵,以 (1) 评估中等和高热率下以 UCO 为燃料的粒子性能,(2) 评估涉及以二氧铀为燃料的粒子的历史试验是否适用于现代以 UCO 为燃料的粒子,(3) 消除温度和热率对粒子瞬态响应的影响,以及 (4) 收集燃料性能模型验证和/或进一步开发所需的数据。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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