An Experimental Study of Assessment of Weld Quality on Fatigue Reliability Analysis of a Nuclear Pressure Vessel

[+] Author and Article Information
Shu-Ho Dai

Department of Mechanical Engineering, Nanjing Institute of Chemical Technology, Nanjing, Jiangsu 210009, People’s Republic of China

J. Pressure Vessel Technol 115(4), 411-414 (Nov 01, 1993) (4 pages) doi:10.1115/1.2929549 History: Received October 22, 1992; Revised June 30, 1993; Online June 17, 2008


The steam generator in a PWR primary coolant system is one of the pieces of equipment made in China for the Qinshan nuclear power plant, Zhejiang. It is a crucial unit belonging to the category of nuclear pressure vessel. The purpose of this research work is to carry out an examination of the weld quality of the steam generator under fatigue loading and to assess its reliability by using experimental results of a fatigue test of the nuclear pressure vessel steel S-271 (Chinese Standard) and of qualified tests of welded seams of a simulated prototype of the bottom closure head of the steam generator. A guarantee of weld quality is proposed as the quality assurance of safety for the China National Nuclear Safety Supervision Bureau. The results of the reliability analysis reported in this work can be taken as supplementary material for a Probabilistic Risk Assessment (PRA) of the Qinshan nuclear power plant [1, 2]. According to the requirement of Provision II-1500 CYCLIC TESTING, ASME Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Power Plant Components [13], a simulated prototype of the bottom closure head of the steam generator was made in this work for the qualified tests. Qualified tests with small sample size present a problem which is difficult to solve in reliability analysis, and are therefore of interest. Here, we offer proposals attempting to solve this problem.

Copyright © 1993 by The American Society of Mechanical Engineers
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