03/02276 Feasibility study of the IE-SASW method for nondestructive evaluation of containment building structures in nuclear power plants

Evaluation of life safety risks to facility occupants, public, and the environment that may result from earthquake events involves both building structures and equipment supported from these structures. But, it is the seismic design of building structures that typically receive the bulk of the attention from the code committees of the national professional organizations and the regulatory authorities. For safety related equipment in nuclear facilities (e.g., Seismic Category I equipment in nuclear power plants and Seismic Performance Category 3 and 4 equipment in the Department of Energy facilities), the seismic design and analysis guidelines and acceptance criteria are well established. But, for Nonseismic Category equipment in nuclear power plants and Seismic Performance Category 1 and 2 equipment in Department of Energy facilities, these have not yet been developed to the same level of completeness and rigor. The code provisions and guidelines available today for these lower class/categories of equipment are briefly, but critically discussed here, along with a comparison of the results of the application of these code provisions.

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Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants

10.2172/968345 ◽

2009 ◽

Author(s):

Stephen Schey

Keyword(s):

Hydrogen Production ◽

Feasibility Study ◽

Nuclear Power ◽

Power Plants ◽

Nuclear Power Plants

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Feasibility Study of Hydrogen Production from Existing Nuclear Power Plants Using Alkaline Electrolysis

10.2172/945378 ◽

2008 ◽

Author(s):

Dana R. Swalla

Keyword(s):

Hydrogen Production ◽

Feasibility Study ◽

Nuclear Power ◽

Power Plants ◽

Nuclear Power Plants ◽

Alkaline Electrolysis

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Feasibility Study on Strain-Based Seismic Design Criteria for Nuclear Components

Energies ◽

10.3390/en13174435 ◽

2020 ◽

Vol 13 (17) ◽

pp. 4435 ◽

Cited By ~ 1

Author(s):

Gyeong-Hoi Koo ◽

Jong-Sung Kim ◽

Yun-Jae Kim

Keyword(s):

Feasibility Study ◽

Seismic Design ◽

Nuclear Power ◽

Power Plants ◽

Nuclear Power Plants ◽

Failure Modes ◽

Seismic Analysis ◽

Design Criteria ◽

Hardening Material ◽

Inelastic Material

In this paper, the feasibility study to develop strain-based seismic design criteria applicable for the components of nuclear power plants are carried out as an alternative rule to the current stress-based criteria. To do this, two acceptance criteria are investigated through the detailed example of an application for the surge line nozzles in a nuclear steam supply system, which are known as one of the seismic fragile components in nuclear power plants. These strain-based seismic design criteria are primarily to prevent two types of failure modes, such as a ductile fracture and a cyclic fatigue-induced damage due to continuous large amplitude cyclic loads during seismic event. Through the example problem, the required procedures are described step-by-step with calculations of an accumulated plastic strain, triaxiality factor by the elasto-plastic seismic analysis using the finite element method. For a precise inelastic seismic analysis, the Chaboche kinematic and Voce isotropic hardening material parameters are identified by the test data and used for an inelastic material model. The results by the strain-based criteria are compared with those by the ASME (American Society of Mechanical Engineers) stress-based design criteria for a service level D limits. From the study, it is expected that the strain-based seismic design method investigated in this paper will be beneficial for the nuclear components, especially when the design basis earthquakes are large enough to cause severe plastic strains at a critical location.

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