4.5 Article Proceedings Paper

Sensitivity studies of modular high-temperature gas-cooled reactor postulated accidents

期刊

NUCLEAR ENGINEERING AND DESIGN
卷 236, 期 5-6, 页码 454-462

出版社

ELSEVIER SCIENCE SA
DOI: 10.1016/j.nucengdes.2005.10.029

关键词

-

向作者/读者索取更多资源

The results of various accident scenario simulations for the two major modular high temperature gas-cooled reactor (HTGR) variants (prismatic and pebble bed cores) are presented. Sensitivity studies can help to quantify the uncertainty ranges of the predicted outcomes for variations in some of the more crucial system parameters, as well as for occurrences of equipment and/or operator failures or errors. In addition, sensitivity studies can guide further efforts in improving the design and determining where more (or less) R&D is appropriate. Both of the modular HTGR designs studied - the 400-MW(t) pebble bed modular reactor (PBMR, pebble) and the 600-MW(t) gas-turbine modular helium reactor (GT-MHR, prismatic) - show excellent accident prevention and mitigation capabilities because of their inherent passive safety features. The large thermal margins between operating and potential damage temperatures, along with the typically very slow accident response times (approximate days to reach peak temperatures), tend to reduce concerns about uncertainties in the simulation models, the initiating events, and the equipment and operator responses. (c) 2006 Elsevier B.V. All rights reserved.

作者

我是这篇论文的作者
点击您的名字以认领此论文并将其添加到您的个人资料中。

评论

主要评分

4.5
评分不足

次要评分

新颖性
-
重要性
-
科学严谨性
-
评价这篇论文

推荐

暂无数据
暂无数据