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Leak-before-break issue

Technical Report ·
DOI:https://doi.org/10.2172/10179155· OSTI ID:10179155

Light water reactors (LWRs) must be designed to accomodate loss of coolant accidents (LOCAs) up to and including a double-ended guillotine break (DEGB) of the largest pipe in the reactor coolant system. Advanced fracture mechanics technology [the leak-before-break (LBB) approach] has been used to demonstrate that there is a very low probability of DEGB in the kinds of piping used in many LWRs. Consequently, some licensing requirements have been relaxed. The issue with respect to new production reactor (NPR) design requirements is whether the LBB approach can be applied to NPR design concepts and whether there is justification for eliminating DEGB as a design basis accident. This paper recommends the following concerning NPR design criteria: Allow LBB analysis as a basis for eliminating pipe whip restraints and other supports designed to mitigate the loads for postulated ruptures in primary system piping; Not allow LBB analysis to eliminate the DEGB LOCA as a design basis accident for the emergency cooling system; and, Not allow LBB analysis to limit the design-basis accident (peak pressure and temperature) for containment and environmental qualifications.

Research Organization:
Los Alamos National Lab., NM (United States); ERC Environmental and Energy Services Co., Albuquerque, NM (United States)
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
W-7405-ENG-36
OSTI ID:
10179155
Report Number(s):
LA-SUB--93-230; ON: DE93019302
Country of Publication:
United States
Language:
English

Similar Records

Belgian experience in applying the {open_quotes}leak-before-break{close_quotes} concept to the primary loop piping
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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
BWR TYPE REACTORS
DESIGN BASIS ACCIDENTS
FRACTURE MECHANICS
LICENSING
LOSS OF COOLANT
PIPE WHIP
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PROBABILITY
PWR TYPE REACTORS
REACTOR SAFETY
RESTRAINTS
SUPPORTS