Published 1993
| Version v1
Report
Comparison of modelling the PMK-2 steam generator by codes RELAP and MELCOR
Description
The RELAP5/MOD2 and MELCOR 1.8.1 codes have been used for simulate the PMK total loss of feedwater with secondary bleed and feed experiments done in a scale-model WWER-440 test facility. Nodalization studies and studies on several-core modelling options were also done. Good agreement was found between the calculations done by RELAP5/MOD2 and MELCOR 1.8.1 JY codes. (orig.) (5 refs., 31 figs.)
Additional details
Publishing Information
- ISBN
- 951-763-788-8
- Imprint Title
- Second international seminar of horizontal steam generator modelling
- Imprint Pagination
- 208 p.
- Journal Page Range
- p. 58-88.
- Report number
- LTKK-TJ--30
Conference
- Title
- 2. international seminar on horizontal steam generator modelling.
- Dates
- 29-30 Sep 1992.
- Place
- Lappeenranta (Finland).
INIS
- Country of Publication
- Finland
- Country of Input or Organization
- Finland
- INIS RN
- 26053114
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; FEEDWATER; LOSS OF COOLANT; M CODES; R CODES; SCALE MODELS; SECONDARY COOLANT CIRCUITS; STEAM GENERATORS; TEST FACILITIES; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; STRUCTURAL MODELS; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS