CONTAIN code calculations for the LA-4 experiment
Description
The CONTAIN code is a system-level analysis tool developed for the USNRC, and is intended for best-estimate prediction of conditions which might occur in the containment building of a nuclear power plant during a severe accident. A key feature of the code is that it models the containment phenomena in an integrated manner. In particular, the CONTAIN code models some of the complex ways that thermal hydraulics and aerosol phenomena interact with each other. The Light Water Reactor Aerosol Containment Experiment (LACE) progarm is a program to aid researchers in their understanding of thermal hydraulic and aerosol behavior within containments. The purpose of this paper is to report on best-estimate LA-4 post-test calculations that have been completed with the most recent version of the CONTAIN code, version 1.11. An analysis of experimental data and review of the blind post-test CONTAIN calculations is used to justify a re-calculation of the experiment and to establish a best-estimate calculation. The best-estimate calculation shows that reasonably good agreement between thermal hydraulic predictions and data can be obtained with the current CONTAIN models by varying experimental parameters within their uncertainties. Furthermore, with the recently added solubility model for hygroscopic aerosols, the best-estimate calculation gives aerosol behavior that is in good agreement with aerosol data. 10 refs., 16 figs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A03/MF A01 as DE90012753; OSTI; INIS; US Govt. Printing Office Dep.
Files
Additional details
Publishing Information
- Imprint Pagination
- 14 p.
- Report number
- SAND--89-3010C
Conference
- Title
- 2. international conference on containment design and operation.
- Dates
- 14-17 Oct 1990.
- Place
- Toronto (Canada).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21090506
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AEROSOLS; BWR TYPE REACTORS; C CODES; COMPUTERIZED SIMULATION; CONTAINMENT; CONTAINMENT BUILDINGS; HEAT TRANSFER; HYDRAULICS; NUCLEAR POWER PLANTS; PARTICLE SIZE; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; STEAM; TEST FACILITIES; VAPOR CONDENSATION
- Descriptors DEC
- ACCIDENTS; BUILDINGS; COLLOIDS; COMPUTER CODES; DISPERSIONS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; SAFETY; SIMULATION; SIZE; SOLS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC04-76DP00789
- Secondary number(s)
- CONF-901024--4.