Published 1992
| Version v1
Journal article
MOST10-Mod1-CS code for 3-D neutronic and 1-D thermal hydraulic calculations for WWER-1000 reactor and coolant system
Description
The MOST10-Mod1-CS code performs thermal hydraulic and 3-D neutron physics calculations for a NPP with a WWER-1000 type reactor. The code simulates the following elements: the reactor, four primary loops, the pressurizer, steam generator primary and secondary sides, core channels and the steam header. The code is primarily designed for reactivity initiated accident calculations. (author) 10 figs., 1 ref
Additional details
Publishing Information
- Journal Title
- Nucleon
- Journal Issue
- no.3
- Journal Page Range
- p. 22-26.
- CODEN
- NLEQEM
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Serbia and Montenegro
- INIS RN
- 24007318
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CALCULATIONS; HYDRAULICS; M CODES; NEUTRON FLUX; NUCLEAR POWER PLANTS; PRESSURIZERS; PRIMARY COOLANT CIRCUITS; REACTIVITY; REACTOR ACCIDENTS; REACTOR KINETICS; SECONDARY COOLANT CIRCUITS; SIMULATION; STEAM GENERATORS; THREE-DIMENSIONAL CALCULATIONS; TRANSIENTS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; KINETICS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS