Uncertainty Quantification for the Doppler Reactivity Feedback Coefficient of MYRRHA

IF 1.2 3区工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Science and Engineering Pub Date : 2024-06-20 DOI:10.1080/00295639.2024.2353987

Luca Fiorito, Matteo Zanetti, Federico Grimaldi, Gert van den Eynde

引用次数: 0

Abstract

Safety analyses of MYRRHA require calculating the reactor temperature feedback coefficients of reactivity associated with power operation. Within this framework, a significant emphasis is put on th...

查看原文本刊更多论文

MYRRHA 多普勒反应反馈系数的不确定性量化

MYRRHA 的安全分析需要计算与功率运行相关的反应堆温度反馈反应系数。在这一框架内，重点强调...

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

Nuclear Science and Engineering 工程技术-核科学技术

CiteScore

2.10

自引率

25.00%

发文量

审稿时长

3 months

期刊介绍： Nuclear Science and Engineering, the research journal of the American Nuclear Society, publishes articles on research and development related to peaceful utilization of nuclear energy, radiation, and alternative energy sources.