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Title: Post Test Analysis of a PCCV Model Dynamically Tested Under Simulated Design-Basis Earthquakes

Conference ·
OSTI ID:1114

In a collaborative program between the United States Nuclear Regulatory Commission (USNRC) and the Nuclear Power Engineering Corporation (NUPEC) of Japan under sponsorship of the Ministry of International Trade and Ihdustry, the seismic behavior of Prestressed Concrete Containment Vessels (PCCV) is being investigated. A 1:10 scale PCCV model has been constructed by NUPEC and subjected to seismic simulation tests using the high performance shaking table at the Tadotsu Engineering Laboratory. A primary objective of the testing program is to demonstrate the capability of the PCCV to withstand design basis earthquakes with a significant safety margin against major damage or failure. As part of the collaborative program, Sandia National Laboratories (SNL) is conducting research in state-of-the-art analytical methods for predicting the seismic behavior of PCCV structures, with the eventual goal of understanding, validating, and improving calculations dated to containment structure performance under design and severe seismic events. With the increased emphasis on risk-informed- regulatory focus, more accurate ch&@erization (less uncertainty) of containment structural and functional integri~ is desirable. This paper presents results of post-test calculations conducted at ANATECH to simulate the design level scale model tests.

Research Organization:
Sandia National Laboratories (SNL), Albuquerque, NM, and Livermore, CA (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC04-94AL85000
OSTI ID:
1114
Report Number(s):
SAND98-2398C; ON: DE00001114
Resource Relation:
Conference: 7th International Symposium Current Issues Related to Nuclear Power Plant Structures, Equipment, and Piping; Raleigh, NC; 12/01-04/1998
Country of Publication:
United States
Language:
English