Modeling of H.B.Robinson-2 Pressure Vessel Benchmark (CROSBI ID 580858)
Prilog sa skupa u zborniku | izvorni znanstveni rad | međunarodna recenzija
Podaci o odgovornosti
Vragolov, Dinka ; Matijević, Mario ; Pevec, Dubravko ; Trontl, Krešimir
engleski
Modeling of H.B.Robinson-2 Pressure Vessel Benchmark
H.B.Robinson-2 Pressure Vessel Benchmark (HBR-2 benchmark) has been chosen for qualification of our methodology for pressure vessel neutron fluence calculations, as required by the U.S. Nuclear Regulatory Commission Regulatory Guide 1.190. The SCALE 6.0 code package was used for modeling of the HBR-2 benchmark. The CSAS6 sequence of the SCALE code package, which includes KENO-VI 3D Monte Carlo code, was used for criticality calculation and for generation of the neutron fission distribution file used as a neutron source-term in later shielding calculation. The ORIGEN-ARP/SCALE isotopic depletion and decay analysis sequence was used with point-depletion code ORIGEN-S to find radioactive decay neutron sources which originate from burned fuel assemblies. The MAVRIC/MONACO Monte Carlo shielding sequence with manual and automatic adjoint-based reduction variance (CADIS) techniques was used for calculation of the critical neutron fluxes in downcomer and cavity regions of H.B.Robinson-2 model. The total neutron fluxes comprise of critical and decay neutron fluxes. The comparison of preliminary calculational results and benchmark results obtained with DORT deterministic transport code showed a good agreement of the total neutron fluxes in downcomer and cavity regions.
pressure vessel neutron fluence; SCALE code package; CSAS6 sequence; KENO-VI 3D Monte Carlo code; ORIGEN; MAVRIC/MONACO
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Podaci o prilogu
319.1-319.10.
2011.
objavljeno
Podaci o matičnoj publikaciji
Proceedings of the 20th International Conference Nuclear Energy for New Europe 2011
Podaci o skupu
International Conference Nuclear Energy for New Europe (20 ; 2011)
poster
12.09.2011-15.09.2011
Bovec, Slovenija