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.2010.06.040Additional 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)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 42013282
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT BUILDINGS; CRACKS; DESIGN; EARTHQUAKES; FRACTURE MECHANICS; FRACTURE PROPERTIES; HEAT TRANSFER; INTEGRALS; LEAK TESTING; LEAKS; MATERIALS TESTING; PICKERING-1 REACTOR; PICKERING-4 REACTOR; PIPES; RELIEF VALVES; SEISMIC ISOLATION; STEAM LINES; STRESS ANALYSIS; THERMAL EXPANSION
- Descriptors DEC
- BUILDINGS; CANDU TYPE REACTORS; CONTAINMENT; CONTROL EQUIPMENT; ENERGY TRANSFER; EQUIPMENT; EXPANSION; FLOW REGULATORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MECHANICAL PROPERTIES; MECHANICS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; PIPELINES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SEISMIC EVENTS; TESTING; THERMAL REACTORS; TUBES; VALVES
Optional Information
- Copyright
- Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.