Pregled bibliografske jedinice broj: 410443
Verification of FA2D Prediction Capability Using Fuel Assembly Benchmark
Verification of FA2D Prediction Capability Using Fuel Assembly Benchmark // Proceedings of International Conference Nuclear Energy for New Europe 2008 / Rožman, Stane ; Žagar, Tomaž ; Žefran, Bojan. (ur.).
Portorož, Slovenija: Nuclear Society of Slovenia, 2008. str. 223.1-223.9 (poster, međunarodna recenzija, cjeloviti rad (in extenso), znanstveni)
CROSBI ID: 410443 Za ispravke kontaktirajte CROSBI podršku putem web obrasca
Naslov
Verification of FA2D Prediction Capability Using Fuel Assembly Benchmark
Autori
Ječmenica, Radomir ; Pevec, Dubravko ; Grgić, Davor ; Konjarek, Damir
Vrsta, podvrsta i kategorija rada
Radovi u zbornicima skupova, cjeloviti rad (in extenso), znanstveni
Izvornik
Proceedings of International Conference Nuclear Energy for New Europe 2008
/ Rožman, Stane ; Žagar, Tomaž ; Žefran, Bojan. - : Nuclear Society of Slovenia, 2008, 223.1-223.9
ISBN
978-961-6207-29-4
Skup
International Conference Nuclear Energy for New Europe 2008
Mjesto i datum
Portorož, Slovenija, 08.09.2008. - 11.09.2008
Vrsta sudjelovanja
Poster
Vrsta recenzije
Međunarodna recenzija
Ključne riječi
burn-up; LWR next generation fuel; benchmark; burnable absorbers; collision probabilities; discrete ordinates; FA2D; TRITON
Sažetak
FA2D is a 2D transport collision probability code developed at Faculty of Electrical Engineering and Computing, University Zagreb. It is used for calculation of cross sections (group constants) at fuel assembly level. The main objective of its development was the capability to generate cross section data to be used for fuel management and safety analyses of PWR reactors. Till now the formal verification of the code predictions capability has not been performed at the fuel assembly level, but the results of fuel management calculations obtained using the FA2D generated cross sections for the NPP Krsko and IRIS reactor are compared against the Westinghouse calculations. Cross section data were used within the NRC’ s PARCS code and satisfactory preliminary results were obtained. This paper presents results of calculations performed for Nuclear Fuel Industries, Ltd., benchmark using FA2D, and SCALE5 TRITON calculation sequence (based on discrete ordinates code NEWT). Nuclear Fuel Industries, Ltd., Japan, have released the LWR Next Generation Fuels Benchmark with the aim to verify prediction capability in nuclear design for extended burnup regions. We performed calculations for two different Benchmark problem geometries – UO2 pin cell and UO2 PWR fuel assembly. The results obtained with two mentioned 2D spectral codes are presented for burnup dependency of infinite multiplication factor, isotopic concentration of important materials and for local peaking factor vs. burnup (in case of fuel assembly calculation).
Izvorni jezik
Engleski
Znanstvena područja
Elektrotehnika
POVEZANOST RADA
Projekti:
036-0361590-1579 - Gospodarenje gorivom standardnih i naprednih nuklearnih reaktora (Pevec, Dubravko, MZO ) ( CroRIS)
036-0361590-1589 - Nuklearne elektrane za održivu proizvodnju električne energije (Feretić, Danilo, MZO ) ( CroRIS)
Ustanove:
Fakultet elektrotehnike i računarstva, Zagreb