Transient Analysis Needs for Generation IV Reactor Concepts

Author:

Siefken L. J.1,Harvego E. A.1,Coryell E. W.1,Davis C. B.1

Affiliation:

1. Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID

Abstract

The importance of nuclear energy as a vital and strategic resource in the U. S. and world’s energy supply mix has led to an initiative, termed Generation IV by the U.S. Department of Energy (DOE), to develop and demonstrate new and improved reactor technologies. These new Generation IV reactor concepts are expected to be substantially improved over the current generation of reactors with respect to economics, safety, proliferation resistance and waste characteristics. Although a number of light water reactor concepts have been proposed as Generation IV candidates, the majority of proposed designs have fundamentally different characteristics than the current generation of commercial LWRs operating in the U.S. and other countries. This paper presents the results of a review of these new reactor technologies and defines the transient analyses required to support the evaluation and future development of the Generation IV concepts. The ultimate objective of this work is to identify and develop new capabilities needed by INEEL to support DOE’s Generation IV initiative. In particular, the focus of this study is on needed extensions or enhancements to SCDAP/RELAP5/3D code. This code and the RELAP5-3D code from which it evolved are the primary analysis tools used by the INEEL and others for the analysis of design-basis and beyond-design-basis accidents in current generation light water reactors.

Publisher

ASMEDC

Cited by 3 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Dynamic Thermal Management for Aerospace Technology: Review and Outlook;Journal of Thermophysics and Heat Transfer;2017-01

2. Dynamic Thermal Management for Aerospace Technology: A Review and Outlook;53rd AIAA Aerospace Sciences Meeting;2015-01-03

3. Analysis of the turbine deblading in an HTGR with the CATHARE code;Nuclear Engineering and Design;2006-03

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