scholarly journals Nuclear reactor options to reduce the risk of proliferation and to succeed current light water reactor technology. Comptroller General's report to the Congress

1979 ◽  
Author(s):  
Not Given Author
Keyword(s):  
Nuclear Reactor ◽  
Light Water Reactor ◽  
Light Water ◽  
Water Reactor ◽  
Reactor Technology

Defense-in-Depth Approach for Use in a Risk-Informed, Technology-Neutral Design and Licensing Framework for New Nuclear Plants

2009 ◽  
Author(s):  
Jim Chapman ◽  
Stephen M. Hess
Keyword(s):  
Integrated Approach ◽  
Regulatory Framework ◽  
Light Water Reactor ◽  
Light Water ◽  
Water Reactor ◽  
Safety Standards ◽  
Reactor Technology ◽  
Nuclear Plants ◽  
Defense In Depth ◽  
Water Reactors

The regulatory framework for the current generation of operating plants and advanced light water reactors (ALWRs) planned for near term construction has evolved over several decades to permit effective regulation of the light water reactor designs. To address other reactor types, development of a framework that possesses the attributes of being technology neutral, risk-informed and performance-based with corresponding processes (regulations and guidance) is ongoing by several U.S. and international organizations. A key design and operating principle which is applied to existing plants and will continue to be applied to future plants is defense-in-depth. The advent of advanced reactor designs, some of which are not based on light water reactor technology, provides incentive for changes in the regulatory framework in several areas, including defense-in-depth practices. To support development of an integrated framework, the Electric Power Research Institute (EPRI) conducted research to identify and assess specific elements of possible technology neutral, risk-informed, performance based frameworks that had been proposed by others. The intent was to develop a preliminary framework based on the results of this review and evaluation and to provide recommendations in areas where additional development and testing would appear to be most beneficial. “Technical Elements of a Risk-Informed, Technology-Neutral Design and Licensing Framework for New Nuclear Plants”, EPRI Report 1016150 documents this research (Reference [1]). For defense-in-depth (D-in-D) existing viewpoints from various sources were compared and an alternative integrated approach which addresses key issues was developed. These alternative views are contained in publications such as NUREG-1860 [2], Regulatory Guide 1.174 [6], IAEA Safety Standards Series No. NS-R-1 [3], IAEA 75-INSAG-3 Revision 1 [4], INSAG-12 [4], and IAEA INSAG-10 [5]. The results of this research support the ongoing efforts to develop standards and guidance for advanced plants with safety characteristics which differ from existing and advanced LWRs.

Auxiliary Beam Stress Improved Laser Welding for Repair of Irradiated Light Water Reactor Components

2019 ◽  
Author(s):  
Jian Chen ◽  
Jonathan Tatman ◽  
Zhili Feng ◽  
Roger Miller ◽  
Wei Tang ◽  
...  
Keyword(s):  
Laser Welding ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
National Laboratory ◽  
Department Of Energy ◽  
Light Water Reactor ◽  
Development Effort ◽  
Light Water ◽  
Water Reactor ◽  
Oak Ridge

Abstract The welding task focuses on development of advanced welding technologies for repair and maintenance of nuclear reactor structural components to safely and cost-effectively extend the service life of nuclear power reactors. This paper presents an integrated research and development effort by the Department of Energy Light Water Reactor Sustainability Program through the Oak Ridge National Laboratory (ORNL) and Electric Power Research Institute (EPRI) to develop a patent-pending technology, Auxiliary Beam Stress Improved Laser Welding Technique, that proactively manages the stresses during laser repair welding of highly irradiated reactor internals without helium induced cracking (HeIC). Finite element numerical simulations and in-situ temperature and strain experimental validation have been utilized to identify candidate welding conditions to achieve significant stress compression near the weld pool during cooling. Preliminary welding experiments were performed on irradiated stainless-steel plates (Type 304L). Post-weld characterization reveals that no macroscopic HeIC was observed.

scholarly journals High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor

2007 ◽  
Vol 155 (3) ◽  
pp. 395-408 ◽  
Author(s):  
David P. Weber ◽  
Tanju Sofu ◽  
Won Sik Yang ◽  
Thomas J. Downar ◽  
Justin W. Thomas ◽  
...  
Keyword(s):  
Nuclear Reactor ◽  
Light Water Reactor ◽  
High Fidelity ◽  
Light Water ◽  
Water Reactor
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