Cycle specific hot channel analysis with TRANSURANUS
Creators
- 1. E.ON Kernkraft GmbH, Hannover (Germany)
- 2. Westinghouse Electric Sweden AB (Sweden)
Description
The aim of the PWR hot channel analysis in the German regulatory framework is to prove that for any conceivable transient in the normal operating domain the fuel temperature stays below the melting temperature and the transient tangential cladding strain remains below its licensing limit. In this paper we demonstrate a methodology on how to prove the requirements of the hot channel analysis on a cycle specific basis. In the first step a limit boundary curve is calculated for the maximum rod peak power as a function of burnup for the melting temperature criterion. A limit boundary plain is calculated for the maximum rod power jump as a function of burnup and pre-transient power level for the strain criterion. These boundary sets are considered to be cycle independent. In the second step a standardized and demanding reactor transient is analyzed for a specific cycle. The maximum rod peak powers and maximum rod power jumps are compared with the limit boundary sets in order to prove the above mentioned licensing requirements. Calculation results for the boundary sets are presented for a 4000 MWth PWR core loaded with Opt. Zirlo U/U-Gd 16x16 fuel assemblies. These results were derived with the help of the computer code TRANSURANUS. The transient fuel parameters were calculated with the CASCADE-3D computer code. (orig.)
Additional details
Additional titles
- Original title (English)
- Jahrestagung Kerntechnik 2011. Dokumentation
Publishing Information
- Imprint Title
- Annual meeting on nuclear technology 2011. Documentation
- Imprint Pagination
- 870 p.
- Journal Page Range
- 6 p.
Conference
- Title
- Annual meeting on nuclear technology 2011
- Original Conference Title
- Jahrestagung Kerntechnik 2011
- Dates
- 17-19 May 2011
- Place
- Berlin (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 42106214
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CONTROL ELEMENTS; EXCURSIONS; FEDERAL REPUBLIC OF GERMANY; FUEL CHANNELS; FUEL CYCLE; FUEL RODS; GADOLINIUM; HOT CHANNEL; MELTING POINTS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR SAFETY; SAFETY MARGINS; STANDARDS; T CODES; TRANSIENTS; URANIUM
- Descriptors DEC
- ACCIDENTS; ACTINIDES; COMPUTER CODES; COOLING SYSTEMS; DEVELOPED COUNTRIES; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EUROPE; FUEL ELEMENTS; METALS; PHYSICAL PROPERTIES; POWER REACTORS; RARE EARTHS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRANSITION TEMPERATURE; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE
Optional Information
- Notes
- Imprint:Jahrestagung Kerntechnik 2011. Dokumentation