Published October 2010 | Version v1
Journal article

Leak-Before-Break analysis for Pickering 'A' Unit 1 and Unit 4 large diameter main steam line pipes

Creators

  • 1. Engineering Mechanics Department, Ontario Power Generation - Nuclear, 889 Brock Road, Pickering, Ontario, L1W 3J2 (Canada)

Description

This paper presents a Leak-Before-Break (LBB) analysis of large diameter main steam line pipes (i.e. NPS 28'' and 30'') running from reactor building to main steam balance header in Pickering nuclear plant Unit 1 and Unit 4. Recent development in LBB technology summarized in U.S. Nuclear Regular Commission report NUREG/CR-6765 was adopted. Based on the tiered approach of LBB philosophy, this LBB analysis belongs to level 2 or level 3 LBB analysis. Detailed fracture tolerance analyses and leakage rate calculations were performed. EPFM (elastic plastic fracture mechanics) theory of J-integral, resistance curve versus ductile crack extension was adopted in carrying out all fracture tolerance analyses. Through-wall cracks in axial and circumferential directions on both straight pipes and elbows were postulated and analyzed. The loads applied on the postulated cracked pipes were obtained from detailed piping stress analysis under deadweight load, design pressure, thermal expansion, seismic design based earthquake (DBE) and thrust load due to the opening of relief valves. J-resistance data were derived from the lowest fracture toughness testing data obtained from Ontario Power Generation's PHT (primary heat transport) LBB material testing programs. A margin of 2 on crack size was chosen in establishing maximum allowable crack sizes. Leakage rates were calculated using SQUIRT Windows Version 1.1 program. The fluid inside the main steam line pipes was assumed single phase steam at 100% quality. One tenth of the calculated leakage rates was proposed as the requirement for minimum leakage detection capability. The paper concludes that the absence of through-wall crack larger than 91.16 mm in length should be maintained in order to ensure the structural integrity of large diameter main steam line pipes. In lieu of this crack size requirement, a reliable leakage detection capability which could quantify mass steam leakage rate of 0.01678 kg per second, or volume leakage rate of 1.01 l/min, should be in place. If both of the above two requirements are met, the Leak-Before-Break of these large diameter main steam line pipes is warranted.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2010.06.040

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2010.06.040;
PII
S0029-5493(10)00472-3;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
240
Journal Issue
10
Journal Page Range
p. 2589-2603
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
4. international topical meeting on high temperature reactor technology
Acronym
HTR 2008
Dates
28 Sep - 1 Oct 2008
Place
Washington, DC (United States)

Optional Information

Copyright
Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.