Published 1991
| Version v1
Journal article
WWER-1000 behaviour simulation during a pressurizer's leak and a cooling system's failure
Creators
- 1. Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. za Yadrena Izsledvaniya i Yadrena Energetika
Description
The WWER-1000 system bahaviour during a leak from the pressurizer relief valve combined with a total loss of offsite power and a failure of the high-pressure pumps has been analysed. RELAP 4/06 and SSYST-2 codes are used. The changes in the most important thermophysical parameters of the primary coolant circuit, reactor core and the fuel elements under these conditions are examined. Tha data obtained indicate that the WWER-1000 fuel rods are not damaged by such transients. 3 figs., 3 refs
Additional details
Publishing Information
- Journal Title
- Yadrena Energiya
- Journal Volume
- 29
- Series
- Yad. Energ.
- Journal Page Range
- 10-14
- ISSN
- 0204-6989
- CODEN
- YAEND
INIS
- Country of Publication
- Bulgaria
- Country of Input or Organization
- Bulgaria
- INIS RN
- 23059596
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- COMPUTER CALCULATIONS; EMERGENCY PLANS; FAILURES; FUEL CANS; FUEL ELEMENTS; HEAT TRANSFER; LEAKS; LOSS OF FLOW; REACTOR COOLING SYSTEMS; REACTOR CORES; TEMPERATURE RANGE 1000-4000 K; THEORETICAL DATA; WWER-5 REACTOR
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS