Published May 1988
| Version v1
Report
Pre-test and post-test calculations performed by RELAP4/MOD6 code for the PMK-NVH standard problem Exercise-1
Creators
- 1. Bylgarska Akademiya na Naukite, Sofia. Inst. za Yadrena Izsledvaniya i Yadrena Energetika
Description
This paper deals with the input preparation and presentation of pre-test and post-test results obtained at the IAEA computer centre on the IAEA Standard Problem Exercise-1 by using the RELAP4/MOD6 code. An intermediate size (7.4%) cold leg break loss of coolant experiment in the PMK-NVH facility at the Central Research Institute for Physics in Budapest without acting hydro-accumulators has been analysed. The pre-test and post-test calculations are compared with the experimental results and the reasons for the pre-test deviations from the experimental data are considered. A much better coincidence of the post-test results with the experiment has been achieved. The experience gained is discussed. (author). 6 refs, 20 figs, 6 tabs
Additional details
Publishing Information
- Imprint Title
- Computer aided safety analysis
- Imprint Pagination
- 194 p.
- Journal Page Range
- p. 79-91.
- Report number
- IAEA-TC--560.02
Conference
- Title
- Technical committee/workshop on computer aided safety analysis.
- Dates
- 25-29 May 1987.
- Place
- Warsaw (Poland).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 20016473
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPARATIVE EVALUATIONS; LOSS OF COOLANT; NUCLEAR POWER PLANTS; R CODES; REACTOR SAFETY EXPERIMENTS; SAFETY ANALYSIS; TEST FACILITIES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; EVALUATION; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; THERMAL POWER PLANTS