Pregled bibliografske jedinice broj: 519340
Modeling of Pool Critical Assembly Pressure Vessel Facility Benchmark
Modeling of Pool Critical Assembly Pressure Vessel Facility Benchmark // Proceedings of the International Conference Nuclear Energy for New Europe / Trkov, Andrej ; Lengar, Igor (ur.).
Ljubljana: Nuclear Society of Slovenia, 2010. str. 207.1-207.8 (poster, međunarodna recenzija, cjeloviti rad (in extenso), znanstveni)
CROSBI ID: 519340 Za ispravke kontaktirajte CROSBI podršku putem web obrasca
Naslov
Modeling of Pool Critical Assembly Pressure Vessel Facility Benchmark
Autori
Vragolov, Dinka ; Matijević, Mario ; Pevec, Dubravko
Vrsta, podvrsta i kategorija rada
Radovi u zbornicima skupova, cjeloviti rad (in extenso), znanstveni
Izvornik
Proceedings of the International Conference Nuclear Energy for New Europe
/ Trkov, Andrej ; Lengar, Igor - Ljubljana : Nuclear Society of Slovenia, 2010, 207.1-207.8
ISBN
978-961-6207-31-7
Skup
International Conference Nuclear Energy for New Europe
Mjesto i datum
Portorož, Slovenija, 06.09.2010. - 09.09.2010
Vrsta sudjelovanja
Poster
Vrsta recenzije
Međunarodna recenzija
Ključne riječi
pressure vessel modeling; Monte Carlo; criticality; SCALE
Sažetak
A Pool Critical Assembly Pressure Vessel Facility Benchmark (PCA 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. The SCALE (Standardized Computer Analysis for Licensing Evaluation) code package, developed at Oak Ridge National Laboratory, was used for modelling of the PCA benchmark. The CSAS6 sequence of the SCALE code package, which includes KENO-VI Monte Carlo code, was used for calculation of equivalent fission fluxes. The calculations were performed using three different models for unit cell of PCA benchmark facility core. The comparison of calculational results and benchmark data showed a good agreement of the calculated and measured equivalent fission fluxes. No systematic decrease of agreements between calculations and measurements with increasing distance of detector from the PCA benchmark facility core was observed for any of unit cell models.
Izvorni jezik
Engleski
Znanstvena područja
Elektrotehnika
POVEZANOST RADA
Projekti:
036-0361590-1579 - Gospodarenje gorivom standardnih i naprednih nuklearnih reaktora (Pevec, Dubravko, MZO ) ( CroRIS)
Ustanove:
Fakultet elektrotehnike i računarstva, Zagreb