scholarly journals Analysis of nuclear power plant component failures

1984 ◽  
Author(s):  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Plant Component ◽  
Component Failures

Development of Experimental and Computational Procedures for Nuclear Power Plant Component Testing Under Flooding Conditions

2017 ◽  
Author(s):  
Antonio Tahhan ◽  
Cody Muchmore ◽  
Larinda Nichols ◽  
Alison Wells ◽  
Gregory Roberts ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Full Scale ◽  
Nuclear Industry ◽  
Small Scale ◽  
Wave Impact ◽  
Plant Component ◽  
Component Testing ◽  
Water Rise

Idaho State University (ISU), with support from Idaho National Laboratory, is actively engaged in enhancing nuclear power plant risk modeling. The ISU team is significantly increasing the understanding of non-containment, nuclear power plant component performance under flooding conditions. The work involves experimentation activities and development of mathematical models, using data from component flooding experiments. The research consists in developing experimentation procedures that comprised small scale component testing, followed by simple and then complex full scale component testing. The research is taking place in the Component Flooding Evaluation Laboratory (CFEL). Tests in CFEL will include water rise, spray, and wave impact experiments on passive and active components. Initial development work focused on small scale components, radios and simulated doors, that served as a low-risk and low-cost proof-of-concept options. Following these tests, full-scale component tests were performed in the Portal Evaluation Tank (PET). The PET is a semi-cylindrical 7500-1 capacity steel tank, with an opening to the environment of 2.4 m. × 2.4 m. The opening allows installation of doors, feedthroughs, pipes, or other components. The first set of experiments with the PET were conducted in 2016 using hollow doors subjected to a water rise scenario. Data collected during the door tests is being analyzed using Bayesian regression methods to determine the parameters of influence and inform future experiments. A practical method of simulating full scale wave impacts on components and structures is also being researched to further enhance CFEL capabilities. Early on, the team determined full scale wave impacts could not be simulated using traditional wave flumes or pools; therefore, closed conduit flow is under consideration. Computational fluid dynamics software is being used to simulate fluid velocities associated with tsunami waves of heights up to 6-m, and to design a wave impact simulation device capable of accurately recreating a near vertical wave section with variable height and fluid velocity. The component flooding simulation activities associated with this project involve use of smoothed particle dynamics codes. These particle-based simulation methods do not require a mesh to be applied to the fluid, which allows for more natural flows to be simulated. Finally, CFEL can be described as a pioneering element, comprised of several ongoing research and experimental projects, that are vital to the development of risk analysis methods for the nuclear industry.

“Making It Work”: The Vital Role of Commissioning in Nuclear Power Programs

2016 ◽  
Vol 2 (4) ◽  
Author(s):  
John H. Moore
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Vital Role ◽  
Special Relationship ◽  
Plant Component ◽  
Term Operation

This paper presents an overview of the duties of a nuclear power plant (NPP) commissioning organization and its special relationship with both the early stages of an NPP project and the long-term operation of such power plants. Decisions made early in the design and procurement process need to be understood by commissioning staff, and their implications need to be incorporated into commissioning programs. Commissioning programs also need to take the steps needed to baseline plant-component ageing programs to facilitate the long-term NPP operation.

Development of an ASME QME-1-2007 Program for Safety Related Active Valve Assemblies for Advanced Plants

2011 ◽  
Author(s):  
L. Ike Ezekoye ◽  
Edward W. Drake
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Mechanical Equipment ◽  
Plant Component ◽  
Valve Assembly ◽  
Active Valve ◽  
The Right

ASME QME-1 “Qualification of Active Mechanical Equipment Used in Nuclear Power Plants” sets forth the requirements and guidelines which could be used to assure that active mechanical equipment is qualified for specified service conditions [1]. As determined by federal regulators and/or nuclear power plant licensees, this Standard could be applied to future nuclear power plants, or existing operating nuclear power plant component replacements, modifications, or additions. Over the years, the standard has gone through various revisions to both clarify and extend the requirements. However, the ASME QME-1-2007 standard significantly altered the qualification process for Active Valve Assemblies. For new nuclear plants, such as the Westinghouse AP1000, the change required a redevelopment of the valve assembly qualification program. This paper examines how the ASME QME-1-2007 valve assembly qualification requirements changed, how this has affected new plant valve assemblies and overall equipment qualification program, and the lessons that have been learned during the redevelopment and implementation of the standard. Specific issues covered in this paper include selecting the qualified valves and adjusting valve actuator qualifications to provide the right inputs to the ASME QME-1-2007 program.

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