佩吕特堆功率增大时TRISO失效率分析

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2025-01-11 DOI:10.1016/j.nucengdes.2025.113842
Fitria Miftasani , Steven Wijaya , Nina Widiawati , Anni Nuril Hidayati , Dany Mulyana , Hakimul Wafda , Anik Purwaningsih , Fajar Al Afghani , Muhammad Ilham Bayquni , Arya Adhyaksa Waskita , Topan Setiadipura
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引用次数: 0

摘要

本研究探讨了在正常运行和减压强制冷却损失(DLOFC)事故情景下,增加PeLUIt反应堆功率对triso包覆燃料颗粒失效率的影响。在本研究中,尽管功率发生变化,但堆芯的几何形状仍然保持不变,同时调整冷却剂速度以保持进出口温度。使用TRIAC-BATAN代码来评估triso包覆燃料颗粒在不同反应堆功率范围从10 MWt到50 MWt下的失效分数。PeLUIt的中子计算使用pebed代码进行,而辐照和DLOFC事故温度则通过pebed 1-D和THERMIX-KONVEX结合pebed代码进行分析。结果表明,在较低的功率下(10 ~ 30 MWt), TRISO颗粒的失效率保持在较低水平,随着功率的增加,失效率的增加幅度很小。然而,在30 MWt以上,观察到失效率呈指数增长,特别是超过40 MWt。在50 MWt时,当燃料温度超过DLOFC期间1600°C的安全阈值时,TRISO颗粒失效会显著增加,并伴有SiC层的降解。
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Analysis of TRISO failure fraction in PeLUIt reactor with increasing power
This study investigates the impact of increasing power in the PeLUIt reactor on the failure fraction of TRISO-coated fuel particles during both normal operation and Depressurized Loss of Forced Cooling (DLOFC) accident scenarios. In this study, the core geometry is preserved despite of the power changes while the coolant velocity is adjusted to maintain the intlet and outlet temperatures. The TRIAC-BATAN code was used to evalute the failure fraction of TRISO-coated fuel particles at various reactor power ranging from 10 MWt to 50 MWt. Neutronic calculations for PeLUIt were conducted using the PEBBED code, while irradiation and DLOFC accident temperatures were analyzed through a combination of PEBBED 1-D and THERMIX-KONVEX, coupled with PEBBED. The results show that at lower power (10 MWt to 30 MWt), the failure fraction of TRISO particles remains low, with minimal increases as power rise. However, above 30 MWt, an exponential increase in failure fraction is observed, particularly beyond 40 MWt. At 50 MWt, when fuel temperatures exceed the safety threshold of 1600 °C during DLOFC, a significant rise in TRISO particle failure occurs, accompanied by degradation of the SiC layer.
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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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