Detailed burnup analysis for assemblies of the supercritical light water reactor
Description
For the present design variant of fuel assemblies of the High Performance Light Water Reactor with coolant and moderator in supercritical state assembly and assembly cluster burnup calculations were performed to get information about k-infinity vs. burnup and power distributions for different moderator and coolant states. The analysis was performed in 2D for UOX and MOX fuel by the Monte Carlo code MCNP5 coupled with the burnup code ''ABBRAND'' developed at IKE. The moderator and coolant state parameters were varied according to typical values in coolant and moderator regions of a three pass core. Single assemblies were moved inside a cluster to simulate bending effects due to temperature gradients etc. to get information about the influence on the power distribution. (orig.)
Additional details
Additional titles
- Original title (English)
- Jahrestagung Kerntechnik 2012. Dokumentation
Publishing Information
- Imprint Title
- Annual meeting on nuclear technology 2012. Documentation
- Imprint Pagination
- 1411 p.
- Journal Page Range
- 7 p.
Conference
- Title
- Annual meeting on nuclear technology 2012
- Original Conference Title
- Jahrestagung Kerntechnik 2012
- Dates
- 22-24 May 2012
- Place
- Stuttgart (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 43117173
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; CONTROL ELEMENTS; COOLANTS; FUEL ASSEMBLIES; M CODES; MIXED OXIDE FUELS; MODERATORS; NEUTRON TRANSPORT THEORY; POWER DISTRIBUTION; REACTIVITY; REACTOR COOLING SYSTEMS; REACTOR CORES; SUPERCRITICAL STATE; TEMPERATURE GRADIENTS; TWO-DIMENSIONAL CALCULATIONS; URANIUM DIOXIDE; WATER COOLED REACTORS
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; COMPUTER CODES; COOLING SYSTEMS; ENERGY SOURCES; ENERGY SYSTEMS; FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; TRANSPORT THEORY; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- Imprint:Jahrestagung Kerntechnik 2012. Dokumentation