Risk assessment of thermal striping in MYRRHA research reactor

Dougdag Mourad; Fernandez Rafael; Lamberts Damien

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Risk assessment of thermal striping in MYRRHA research reactor

机译：MYRRHA研究堆热汽提的风险评估

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摘要

The thermal striping is one of the problems encountered in nuclear facilities. It may affect the reactor main components structural integrity and, sometimes, it can cause their rapid failure.

机译：热剥离是核设施中遇到的问题之一。它可能会影响反应堆主要部件的结构完整性，有时甚至会导致其快速失效。

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来源
《Nuclear Engineering and Design》 |2017年第8期|40-47|共8页
作者
Dougdag Mourad; Fernandez Rafael; Lamberts Damien;
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作者单位

Nucl Res Ctr Birine, BP 180 Ain Oussera, Djelfa, Algeria;

CEN SCK, Belgian Nucl Res Ctr, Boeretang 200, B-2400 Mol, Belgium;

CEN SCK, Belgian Nucl Res Ctr, Boeretang 200, B-2400 Mol, Belgium;

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收录信息美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
原文格式 PDF
正文语种 eng
中图分类
关键词
Thermal striping; Safety analysis; MYRRHA/LBE; Fatigue; Fatigue curve; RCC-MRx; Nuclear engineering;

机译：热剥离;安全性分析;MYRRHA / LBE;疲劳;疲劳曲线;RCC-MRx;核工程;
入库时间 2022-08-18 00:41:22

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1. Coupled system thermal-hydraulic/CFD analysis of a protected loss of flow transient in the MYRRHA reactor [J] . Toti A., Vierendeels J., Belloni F. Annals of nuclear energy . 2018,第AUGa期

机译：MYRRHA反应堆中受保护的瞬态流失损失的系统热工/液压耦合分析
2. Thermal-hydraulic study of the LBE-cooled fuel assembly in the MYRRHA reactor: Experiments and simulations [J] . Pacio J., Wetzel T., Doolaard H., Nuclear Engineering and Design . 2017,第FEBa期

机译：MYRRHA反应堆中LBE冷却燃料组件的热工液压研究：实验和模拟
3. Assessment of the enhanced DHRS configuration for MYRRHA reactor [J] . Bubelis E., Jaeger W., Bandini G., Nuclear Engineering and Design . 2016,第OCTa期

机译：评估MYRRHA反应堆的强化DHRS配置
4. DEVELOPMENT AND PRELIMINARY VALIDATION OF A STH-CFD COUPLING METHOD FOR MULTISCALE THERMAL-HYDRAULIC SIMULATIONS OF THE MYRRHA REACTOR [C] . A. Toti, J. Vierendeels, F. Belloni International conference on nuclear engineering . 2016

机译：桃金娘反应器多尺度热工水力模拟的STH-CFD耦合方法的开发及初步验证
5. APPLICATION OF IMPORTANCE MEASURES TO NUCLEAR REACTOR SYSTEMS AND THE DEVELOPMENT OF SYSTEMS PERFORMANCE STANDARDS BASED ON PROBABILISTIC RISK ASSESSMENTS. [D] . WHITLEY, ROBERT HOYT. 1984

机译：重要措施在核反应堆系统中的应用以及基于概率风险评估的系统性能标准的开发。
6. Guidelines for Exposure Assessment in Health Risk Studies Following a Nuclear Reactor Accident [O] . André Bouville, Martha S. Linet, Maureen Hatch, 2014

机译：核反应堆事故后健康风险研究中暴露评估的准则
7. LARGE EDDY SIMULATION OF THERMAL STRIPING IN THE UPPER PLENUM OF FAST REACTOR [O] . S.K. Choi, J.W. Han, D. Kim, 2014

机译：快速反应器上层热条纹的大涡模拟
8. Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs [R] . 1994

机译：第二十一届水反应堆安全信息会议记录：第1卷，全体会议;先进反应堆研究;先进的控制系统技术;先进的仪器仪表和控制硬件;人为因素研究;概率风险评估主题;热工水力学;高级无源轻水堆的热工水力研究

Risk assessment of thermal striping in MYRRHA research reactor

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