Comparison of neutronics performance of various TRISO fuels

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2025-01-08 DOI:10.1016/j.nucengdes.2025.113825
Yan-Xin Chen , Shin-Rong Wu , Jason Chao , Der-Sheng Chao , Jhao-Yang Hong , Jenq-Horng Liang
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Abstract

TRISO (Tristructural Isotropic) particle fuel is a type of advanced nuclear fuel developed for High-Temperature Gas-Cooled Reactors (HTGRs). Its robust containment properties make TRISO particle fuel a promising candidate for Accident-Tolerant Fuels (ATFs) for next-generation reactors. In this study, the physics model of HTTR was established with the Monte Carlo code MCNP6.2 to evaluate the neutronic properties when utilizing various TRISO form fuels in High-Temperature Test Reactor (HTTR). The fuels considered in this study include UO2, UC, and UN embedded in the core of TRISO particles. Moreover, the UC fuel is coated with TiN (UC_TiN), while the UN fuel is coated with ZrC (UN_ZrC). These two fuel types have been recognized as having manufacturing prospects, so ascertaining the effects of these coating materials on their neutronic performance before conducting practical applications is necessary. The results indicate that the isothermal temperature coefficients of the UC and UN fuels remained negative during the experimental operation, particularly −0.022 to −0.032 lower than the UO2_TRISO fuel in the operational temperature, −0.016 to −0.043 lower in the condition when it exceeded the temperature of operational condition, shows the safety aspect of the utilization of ATFs. The effective multiplication factor of each fuel remained nearly constant during 660 EFPD; each fuel, accounting for the initial drop, has a Δk/kfinal<10% indicating that the fuel replacement that occurred during the operation procedure maintained stability. Moreover, the neutron spectrum at the Beginning of Cycle (BOC) and End of Cycle (EOC) showed that the significant difference in the effective multiplication factor of UC_TRISO and UC_TiN was caused by the coating layers. The moderator-to-fuel ratio provides evidence that the difference between the fuels was caused by the fuel design instead of operational conditions, indicating that the heavy metal coating might not be suitable for HTGRs compared to TRISO coating. The spent fuel analysis is discussed to clarify fuel variations, which shows that the minor actinides of each fuel have increased about 4.2 %–27.7 % in comparison with the UO2_TRISO, based on these neutronic mechanisms and calculation analysis, thus providing compelling evidence supporting the feasibility of applying ATFs in HTGRs.
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各种TRISO燃料的中子性能比较
TRISO(三结构各向同性)颗粒燃料是为高温气冷堆(htgr)开发的一种先进核燃料。其坚固的密封性能使TRISO颗粒燃料成为下一代反应堆耐事故燃料(atf)的有希望的候选者。本研究利用蒙特卡罗代码MCNP6.2建立了高温试验堆(HTTR)的物理模型,以评估高温试验堆(HTTR)中使用各种TRISO形式燃料时的中子特性。本研究考虑的燃料包括嵌入在TRISO颗粒核心的UO2、UC和UN。此外,UC燃料涂有TiN (UC_TiN),而UN燃料涂有ZrC (UN_ZrC)。这两种燃料已被公认为具有制造前景,因此在进行实际应用之前,有必要确定这些涂层材料对其中子性能的影响。结果表明,UC和UN燃料的等温温度系数在实验运行期间保持为负值,特别是在运行温度下比UO2_TRISO燃料低- 0.022 ~ - 0.032,超过运行温度时比UO2_TRISO燃料低- 0.016 ~ - 0.043,表明了ATFs利用的安全性。在660 EFPD时,每种燃料的有效倍增系数基本保持不变;每种燃料,占初始下降,有Δk/kfinal<;10%,表明在运行过程中发生的燃料更换保持稳定。此外,循环开始(BOC)和循环结束(EOC)时的中子谱表明,UC_TRISO和UC_TiN的有效倍增因子的显著差异是由涂层引起的。缓燃比证明了两种燃料之间的差异是由燃料设计造成的,而不是由运行条件造成的,这表明与TRISO涂层相比,重金属涂层可能不适合htgr。通过对乏燃料进行分析,明确了燃料的变化,结果表明,基于这些中子机制和计算分析,与UO2_TRISO相比,每种燃料的微量锕系元素增加了4.2% - 27.7%,从而为支持在htgr中应用ATFs的可行性提供了有力的证据。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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