Analytical predictions for the performance of a reinforced concrete containment model subject to overpressurization
Description
Under the sponsorship of the US Nuclear Regulatory Commission, Sandia National Laboratories is investigating methods for predicting the structural performance of nuclear reactor containment buildings under hypothesized severe accident conditions. As part of this program, a 1/6th-scale reinforced concrete containment model will be pressurized to failure in early 1987. Data generated by the test will be compared to analytical predictions of the structural response in order to assess the accuracy and reliability of the analytical techniques. As part of the pretest analysis effort, Sandia has conducted a number of analyses of the containment structure using the ABAQUS general purpose finite element code. This paper describes results from a nonlinear axisymmetric shell analysis as well as the material models and failure criteria used in conjunction with the analysis
Availability note (English)
Available from NTIS, PC A02; 3 as DE87006120.
Files
Additional details
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- SAND--86-1648C
Conference
- Title
- international conference on structural mechanics in reactor technology.
- Acronym
- 9. SMIRT
- Dates
- 17-21 Aug 1987.
- Place
- Lausanne (Switzerland).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19005713
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; CONCRETES; CONTAINMENT BUILDINGS; FAILURES; FINITE ELEMENT METHOD; PRESSURE DEPENDENCE; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; SCALE MODELS; THEORETICAL DATA
- Descriptors DEC
- BUILDING MATERIALS; BUILDINGS; CONTAINMENT; DATA; ENRICHED URANIUM REACTORS; INFORMATION; MATERIALS; NUMERICAL DATA; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Paper copy only, copy does not permit microfiche production.
- Secondary number(s)
- CONF-870812--4.