Calculation of the response of the WWER-440/213 reactor core to an accident associated with main steam header break by means of the ATHLET system code in combination with with the three-dimensional reactor dynamics code DYN3D
Description
A survey is given of the behavior of the reactor core during an accident associated with main steam header break. This problem is a benchmark exercise for the verification of thermohydraulic system codes connected with three-dimensional hexagonal reactor dynamics codes. The accident is initiated by a symmetrical break of the main steam header at the end of the 1st fuelling cyclein the hot shutdown condition with the control rod groups fully inserted except for group 4. The calculations were performed by using the externally coupled codes ATHLET Mod. 1.1 Cycle C and DYN3DH1.1/M3. The two codes are described at their external coupling is outlined. The standard WWER-440/213 input deck of the ATHLET code was used. The tresults of steady-state calculations as well as burnup calculations are given. The analysis of the transient process is aimed at the time behavior of safety related parameters in selected components of the primary and secondary circuits as well as at the global parameters of the reactor core and behavior in selected fuel assemblies
Availability note (English)
Available from Nuclear Research Institute Rez, 250 68 Rez, Czech Republic; e-mail contact: ret@nri.czAdditional details
Additional titles
- Original title (Czech)
- Vypocet odezvy aktivni zony reaktoru WWER-440/213 na havarii spojenou s prasknutim parniho potrubi pomoci systemoveho kodu ATHLET spojeneho s trirozmernym reaktorove dynamickym kodem DYN3D
Publishing Information
- Imprint Pagination
- [48 p.]
- Report number
- UJV--11166-R,T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 31043406
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- A CODES; BENCHMARKS; BORIC ACID; BURNUP; COMPUTER CALCULATIONS; CONFIGURATION; CONTROL ELEMENTS; COOLANT LOOPS; D CODES; DESIGN BASIS ACCIDENTS; NEUTRON FLUENCE; NEUTRON FLUX; PIPES; PRIMARY COOLANT CIRCUITS; REACTOR CORES; RUPTURES; SECONDARY COOLANT CIRCUITS; STEAM GENERATORS; STEAM LINES; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE RANGE 1000-4000 K; THREE-DIMENSIONAL CALCULATIONS; TRANSIENTS; TUBES; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; BOILERS; BORON COMPOUNDS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; OXYGEN COMPOUNDS; PIPELINES; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; TUBES; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 tabs., 63 figs., 16 refs.