Conformity between LR0 mock-ups and VVERS NPP RPV neutron flux attenuation
Creators
- Belousov, Sergey1
- Iilieva, Krassimira1
- Kkirilova, Desislava1
- European Commission, Joint Research Centre, Institute for Energy, Westerduinweg 3, 1755 LE, Petten (Netherlands)
- European Working Group on Reactor Dosimetry - EWGRD (European Commission (EC))
- ASTM Committee E1O on Nuclear Technology and Applications, ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA, 19428-2959 (United States)
- 1. Institute for Nuclear Research and Nuclear Energy, Bulgarian Academy of Sciences, 72 Tsarigradsko shosse blvd., 1784 Sofia (Bulgaria)
Description
The conformity of the mock-up results and those for reactor pressure vessel (RPV) of nuclear power plants (NPP) has been evaluated in order to qualify if the mock-ups data could be used for benchmark's purpose only, or/and for simulating of the NPP irradiation conditions. Neutron transport through the vessel has been calculated by the three-dimensional discrete ordinate code TORT with problem oriented multigroup energy neutron cross-section library BGL. Flux/fluence and spectrum shape represented by normalized group fluxes in the multigroup energy structure, for neutrons with energy above 0.5 MeV, have been used for conformity analysis. It has been demonstrated that the relative difference of the attenuation factor as well as the group fluxes did not exceed 10% at all considered positions for VVER-440. For VVER-1000, it has been obtained the same consistency, except for the location behind the RPV. The flux attenuation behind the RPV is 18% higher than the mock-up attenuation. It has been shown that this difference arises from the dissimilarity of the biological shielding. The obtained results have demonstrated that the VVERs' mock-ups are appropriate for simulating the NPP irradiation conditions. The mock-up results for VVER-1000 have to be applied more carefully i.e. taking into account the existing peculiarity of the biological shielding and RPV attenuation azimuth dependence. (author)
Availability note (English)
Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addressesAdditional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- INIS-XE-ISRD--13
Conference
- Title
- 13. International Symposium on Reactor Dosimetry
- Acronym
- ISRD-13
- Dates
- 25-29 May 2008
- Place
- Akersloot (Netherlands)
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- France
- INIS RN
- 54030229
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BENCHMARKS; BIOLOGICAL SHIELDING; DISCRETE ORDINATE METHOD; IRRADIATION; MEV RANGE; NEUTRON FLUX; NEUTRON TRANSPORT; NEUTRONS; NUCLEAR DATA COLLECTIONS; NUCLEAR POWER PLANTS; PRESSURE VESSELS; SPACE DEPENDENCE; SPECTRA; THREE-DIMENSIONAL CALCULATIONS; WWER TYPE REACTORS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; CONTAINERS; ELEMENTARY PARTICLES; ENERGY RANGE; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FACILITIES; NUCLEONS; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; RADIATION TRANSPORT; REACTORS; SHIELDING; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs.