Overpressurization performance of containment structures
- 1. UKAEA Safety and Reliability Directorate, Culcheth (UK)
Description
The containment building of a PWR is the outermost engineered barrier between the reactor and the environment. The most important element of such a containment system is the pressure boundary structure and its associated seals and penetrations. This containment structure is designed deterministically to withstand a number of loads and load combinations of which the dominant one is generally the internal pressure due to the double-ended guillotine break in one of the primary circuit loops. Typically, the design basis large LOCA produces a peak pressure increase in the region of 0.3 MPa in some 10 seconds and with a duration of up to a few tens of seconds. The assessment of overpressure performance of the containment structure is a key component of the PWR safety case, and is usually carried out by estimating a static factor of safety to some failure limit state. These estimates can be made using simple force-balance calculations or complicated finite element calculations, and both approaches have merit. In this paper we examine these approaches and discuss their value in estimating failure pressures and failure modes for a variety of internal pressurization transients. This discussion covers both general design and risk considerations and is illustrated by numerical examples taken from previous and on-going analysis
Additional details
Publishing Information
- ISBN
- 92-825-7312-5
- Imprint Title
- Studies of severe accidents in light-water reactors
- Imprint Pagination
- 292 p.
- Journal Page Range
- p. 169-182.
- Report number
- EUR--11019
Conference
- Title
- Seminar concerning safety studies on severe accidents in light-water reactors.
- Dates
- 10-12 Nov 1986.
- Place
- Brussels (Belgium).
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- European Commission (EC), Brussels (Belgium)
- INIS RN
- 19073139
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT BUILDINGS; FINITE ELEMENT METHOD; LOSS OF COOLANT; PRESSURIZATION; PWR TYPE REACTORS; RISK ASSESSMENT; TRANSIENTS; UKAEA
- Descriptors DEC
- ACCIDENTS; BUILDINGS; CONTAINMENT; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; NUMERICAL SOLUTION; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; UNITED KINGDOM ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS