Published 1990
| Version v1
Miscellaneous
Thermal-hydraulic analysis of the LACE experiments and its fall-out on the safety analysis of the LWRs containment system
- 1. Pisa Univ. (Italy). Dipt. di Costruzioni Meccaniche e Nucleari
- 2. ENEA, Rome (Italy)
Description
The main results of the LACE analysis are reported in this work. A brief description of the way the four analyzed tests were performed is necessary to the understanding of the results. The main section of this work deals with the analysis of the thermal-hydraulic results of the tests. The conclusions have been pointed out especially during official participation to various international exercises performed as part of the project. Three levels of conclusions are reported in the final section of this report, focussing on the possible fall-outs of the LACE program results on LWRs safety analysis and qualification of best estimate (BE) computer codes, in particular of the FUMO one. (author). 13 refs., 16 figs
Additional details
Publishing Information
- ISBN
- 0-919784-21-6; 0-919784-22-4
- Imprint Title
- Proceedings of the 2. international conference on containment design and operation. Vol. 1,2
- Imprint Pagination
- [1326 p.].
- Journal Page Range
- [14 p.].
- Report number
- INIS-mf--14838
Conference
- Title
- 2. International conference on containment design and operation.
- Dates
- 14-17 Oct 1990.
- Place
- Toronto, ON (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 27066123
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AEROSOLS; COMPUTERIZED SIMULATION; CONTAINMENT SYSTEMS; CONTAINMENT SYSTEMS EXPERIMENT; COORDINATED RESEARCH PROGRAMS; DESIGN BASIS ACCIDENTS; F CODES; HEAT TRANSFER; HYDRAULICS; LEAKS; POWER REACTORS; PRESSURE SUPPRESSION; PRESSURIZATION; SAFETY ANALYSIS; THERMODYNAMICS; VERIFICATION; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; COLLOIDS; COMPUTER CODES; CONTAINMENT; DISPERSIONS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; REACTOR ACCIDENTS; REACTOR SAFETY EXPERIMENTS; REACTORS; RESEARCH PROGRAMS; SIMULATION; SOLS