Published January 1991
| Version v1
Journal article
Mathematical model of the primary coolant circuit hydrodynamic state under accidents with loss of coolant at NPPs with WWER type reactors
Description
The KIPR program complex designed for calculational analysis of thermohydraulic processes in the primary coolant circuits of the WWER type reactor at the stage of after-heat removal in the case of an accident with loss of coolant, is briefly described. All technological equipment and physical processes are conventionally divided into groups, each of them being described by a separate functional modulus. When developing the mathematical model, the basic aspects of quasistationary method of coolant flow calculation are used. The coolant state is described using density and pressure values averaged over the volume
Additional details
Additional titles
- Original title (Russian)
- Математическая модел' гидродинамического состояния 1-го контура при авариях с течью теплоносителя на AEhS с VVEhR
Publishing Information
- Journal Title
- Ehlektricheskie Stantsii
- Journal Issue
- no.1
- Journal Page Range
- p. 27-31.
- ISSN
- 0013-5372
- CODEN
- EKSTAP
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 24007335
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- ALGORITHMS; COMPUTER CALCULATIONS; HIGH PRESSURE; HYDRAULICS; K CODES; LOSS OF COOLANT; MEDIUM PRESSURE; NUMERICAL SOLUTION; PRESSURE DROP; PRIMARY COOLANT CIRCUITS; TIME DEPENDENCE; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS