Naslov
PWR Pressure Vessel and Biological Shield Dose Rates Modelling Using SCALE6/FW-CADIS Methodology

Autori
Matijević, Mario ; Pevec, Dubravko ; Trontl, Krešimir

Vrsta, podvrsta i kategorija rada
Radovi u zbornicima skupova, cjeloviti rad (in extenso), znanstveni

Izvornik
21st International Conference Nuclear Energy for New Europe Ljubljana 2012 Book of Abstracts / Nuclear Society of Slovenia - Ljubljana : Nuclear Society of Slovenia, 2012, 14-14

Skup
21st International Conference Nuclear Energy for New Europe Ljubljana 2012

Mjesto i datum
Ljubljana, Slovenija, 05.09.2012. - 07.09.2012

Vrsta sudjelovanja
Poster

Vrsta recenzije
Međunarodna recenzija

Ključne riječi
pressurized water reactor; neutron transport; dose rates; SCALE6; CADIS; Monte Carlo; variance reduction

Sažetak
Radiation induced damage to the reactor pressure vessel (RPV) by fast neutron fluence is a main factor when considering lifetime extension for nuclear power plants. This paper is addressing feasibility of modelling a generic (typical) pressurized water reactor (PWR) and predicting dose rates in RPV and biological shield using the SCALE6 (Standardized Computer Analysis for Licensing Evaluation) code package, developed at Oak Ridge National Laboratory. For the purpose of this calculation, the dose rates resulting from neutron and photon sources from operating reactor must be determined. The structural identification of reactor core, implementation of advanced variance reduction methodology and visualization of mesh tally results were necessary steps. The CSAS6 sequence of the SCALE6 code package, which includes KENO-VI Monte Carlo code, as well as MAVRIC/MONACO shielding sequence, was used for calculation of neutron and photon dose rates. MAVRIC is a based on Monte Carlo transport code MONACO with integrated SN code Denovo for automatic generation of space-energy variance reduction (VR) parameters using CADIS (Consistent Adjoint Driven Importance Sampling) and FW-CADIS methodology. The criticality and shielding analysis were performed based on general purpose ENDF/B-VII.0 library. Investigative calculations were performed using different placement of the adjoint source. The reactor core periphery and internals of RPV were analyzed. The benefit of using FW-CADIS was also studied, where adjoint source was inversely weighted by expected dose rate from deterministic forward Denovo run. The FW-CADIS methodology showed improved results over those using standard CADIS approach in terms of obtaining global results with small Monte Carlo uncertainties.

Izvorni jezik
Engleski

Znanstvena područja
Elektrotehnika

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