Published September 2016
| Version v1
Journal article
Qualification of coupled 3D neutron kinetic/thermal hydraulic code systems by the calculation of a VVER-440 benchmark. Re-connection of an isolated loop
Creators
- 1. National Research Centre 'Kurchatov Institute', Moscow (Russian Federation)
- 2. UJV Rez, a.s., Rez (Czech Republic)
- 3. Helmholtz-Zentrum Dresden-Rossendorf (HZDR) e.V., Dresden (Germany)
Description
The 7th AER dynamic benchmark is a continuation of the efforts to validate the codes systematically for the estimation of the transient behavior of VVER type nuclear power plants. The main part of the benchmark is the simulation of the re-connection of an isolated circulation loop with low temperature in a VVER-440 plant. This benchmark was calculated by the National Research Centre ''Kurchatov Institute'' (with the code ATHLET/BIPR-VVER), UJV Rez (with the code RELAP5-3D copyright) and HZDR (with the code DYN3D/ATHLET). The paper gives an overview of the behavior of the main thermal hydraulic and neutron kinetic parameters in the provided solutions.
Additional details
Publishing Information
- Journal Title
- Kerntechnik (1987)
- Journal Volume
- 81
- Journal Issue
- 4
- Journal Page Range
- p. 407-417
- ISSN
- 0932-3902
- CODEN
- KERNEU
Conference
- Title
- 25. AER symposium 2015
- Dates
- 13-16 Oct 2015
- Place
- Balatongyoeroek (Hungary)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 47117176
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COMPUTER CODES; CONVECTION; COOLANT LOOPS; COOLANTS; FLOW RATE; FLUID FLOW; FUEL ASSEMBLIES; NEUTRON TRANSPORT THEORY; NUCLEAR POWER; REACTOR CORES; REACTOR KINETICS; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; TIME DEPENDENCE; WATER; WWER TYPE REACTORS
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; HYDROGEN COMPOUNDS; KINETICS; MASS TRANSFER; MECHANICS; OXYGEN COMPOUNDS; POWER; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS