Reliability analysis of containment strength
Description
The Sequoyah and McGuire ice condenser containment vessels were designed to withstand pressures in the range of 12 to 15 psi. Since pressures of the order of 28 psi were recorded during the Three Mile Island incident, a need exists to more accurately define the strength of these vessels. A best estimate and uncertainty assessment of the strength of the containments were performed by applying the second moment reliability method. Material and geometric properties were supplied by the plant owners. A uniform static internal pressure was assumed. Gross deformation was taken as the failure criterion. Both approximate and finite element analyses were performed on the axisymmetric containment structure and the penetrations. The predicted strength for the Sequoyah vessel is 60 psi with a standard deviation of 8 psi. For McGuire, the mean and standard deviations are 84 psi and 12 psi, respectively. In an Addendum, results by others are summarized and compared and a preliminary dynamic analysis is presented
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A12/MF A01 - GPO $7.50 as DE83000521.
Files
Additional details
Publishing Information
- Imprint Pagination
- 265 p.
- Report number
- NUREG/CR--1891
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14788300
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTAINMENT BUILDINGS; FAILURES; ICE CONDENSERS; MC GUIRE-1 REACTOR; MC GUIRE-2 REACTOR; PRESSURE GRADIENTS; RELIABILITY; SEQUOYAH-1 REACTOR; SEQUOYAH-2 REACTOR; STRESS ANALYSIS
- Descriptors DEC
- CONTAINMENT; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; STEAM CONDENSERS; THERMAL REACTORS; VAPOR CONDENSERS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- IS--4753.