Capability of the coupled code system ATHLET-QUABOX/CUBBOX for safety analysis
Creators
- 1. Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Garching (Germany)
Description
There exists a tendency to perform accident analysis of NPP by best estimate codes, that decreases the conservatism of performing calculations and allows more realistic simulation of transients. A necessary step for this approach is the comprehensive validation of the computer codes and the coupling of thermo-hydraulic plant system codes with 3D neutronics models. The application of coupled code systems is mandatory for the analysis of accident conditions which are determined by a strong coupling between neutronics of the reactor core and thermo-hydraulics of the primary circuit, especially, when asymmetrical processes take place in the core leading to strongly space-dependent power generation. The paper gives an overview on the development of the coupled 3D neutronics and fluid-dynamic system code in GRS, in particular, the work is presented performed on the basis of the system code ATHLET and the 3D reactor core model QUABOX/CUBBOX, both developed in GRS. In addition, the experiences from applications in accident analysis are summarized and further developments are discussed. (author)
Additional details
Identifiers
Publishing Information
- ISBN
- 92-0-101207-1
- Imprint Title
- Use and development of coupled computer codes for the analysis of accidents at nuclear power plants. Proceedings of a technical meeting
- Imprint Pagination
- 321 p.
- Journal Page Range
- [8 p.]
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1539(companion CD)
Conference
- Title
- Technical meeting on use and development of coupled computer codes for the analysis of accidents at nuclear power plants
- Dates
- 26-28 Nov 2003
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 38096584
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; GESELLSCHAFT FUER ANLAGEN- UND REAKTORSICHERHEIT; HYDRAULICS; NUCLEAR POWER PLANTS; POWER GENERATION; REACTOR ACCIDENTS; REACTOR CORES; SAFETY ANALYSIS; SPACE DEPENDENCE; STRONG-COUPLING MODEL; VALIDATION
- Descriptors DEC
- ACCIDENTS; FLUID MECHANICS; GERMAN FR ORGANIZATIONS; MATHEMATICAL MODELS; MECHANICS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; PARTICLE MODELS; POWER PLANTS; REACTOR COMPONENTS; SIMULATION; TESTING; THERMAL POWER PLANTS
Optional Information
- Notes
- 9 refs, 3 figs