Proceedings of a specialist meeting on leak before break in reactor piping and vessels
Description
This Specialist Meeting was organised by EDF, Framatome and CEA with the participation of SFEN, and it was sponsored jointly by the CEC DG XI, Nuclear Electric, IAEA, US NRC, and by the Principal Working Group 3 (PWG-3) on Reactor Component Integrity of the NEA CSNI. The activities of PWG-3 fall into three main areas: Non-Destructive Examination (NDE), fracture analysis and aging/materials degradation. In fracture analysis, the activities are organised by the Fracture Analysis Group, and include the round robins on Fracture Analysis of Large Scale International Reference Experiments (FALSIRE). The topic of the workshop falls mainly into the second area of fracture analysis. The objective of the meeting was to present the current state of the art in Leak-Before-Break (LBB) methodology development, validation, and application in an international forum. With particular emphasis on industrial applications and regulatory policies, the seminar provided an opportunity to compare approaches, experiences, and codifications developed by different countries. The seminar was organized into four topic areas: status of LBB applications; technical issues in LBB methodology; complementary requirements (leak detection and inspection); LBB assessment and margins. As a result of this seminar, an improved understanding of LBB gained through sharing of different viewpoints from different countries, permits consideration of: simplified pipe support design and possible elimination of loss-of-coolant-accident (LOCA) mechanical consequences for specific cases; defense-in-depth type of applications without support modifications; support of safety cases for plants designed without the LOCA hypothesis. In support of these activities, better estimates of the limits to the LBB approach should follow, as well as an improvement in codifying methodologies. The formal proceedings of the meeting were published by US NRC as a NUREG report (NUREG/CP--0155). This includes the final versions of papers and the summaries by the session chairmen. This CSNI report consists of the papers received at the meeting. Among those, five papers have been identified which are not in the NUREG report or which are presented differently. These papers have been entered in INIS as a complement to the formal proceedings. This CSNI report represents also an access to the full text of the other presentations reported in the NUREG report
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Additional details
Publishing Information
- Imprint Pagination
- 691 p.
- Report number
- NEA-CSNI-R--1995-18
Conference
- Title
- Specialist meeting on leak before break in reactor piping and vessels
- Dates
- 9-11 Oct 1995
- Place
- Lyon (France)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 43012290
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Is Lead record
- Yes
- Descriptors DEI
- BWR TYPE REACTORS; CRACK PROPAGATION; ECCS; FRACTURE MECHANICS; IN-SERVICE INSPECTION; LEADING ABSTRACT; LEAK TESTING; PIPES; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR MATERIALS; REACTOR OPERATION; REACTOR SAFETY; RISK ASSESSMENT; SAFETY ANALYSIS; SENSITIVITY ANALYSIS; SYSTEM FAILURE ANALYSIS; WWER TYPE REACTORS
- Descriptors DEC
- ABSTRACTS; ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; INSPECTION; MATERIALS; MECHANICS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SYSTEMS ANALYSIS; TESTING; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- OCDE-GD--96-11