Pregled bibliografske jedinice broj: 955658
Radioactive Inventory Data for Severe Accident and Consequence Calculation Codes
Radioactive Inventory Data for Severe Accident and Consequence Calculation Codes // Book of Abstracts of the 26th International Conference Nuclear Energy for New Europe NENE2017
Bled, Slovenija, 2017. str. 120-120 (poster, međunarodna recenzija, sažetak, znanstveni)
CROSBI ID: 955658 Za ispravke kontaktirajte CROSBI podršku putem web obrasca
Naslov
Radioactive Inventory Data for Severe Accident and Consequence Calculation Codes
Autori
Grgić, Davor ; Ječmenica, Radomir ; Vlahović, Štefica ; Bašić, Ivica
Vrsta, podvrsta i kategorija rada
Sažeci sa skupova, sažetak, znanstveni
Izvornik
Book of Abstracts of the 26th International Conference Nuclear Energy for New Europe NENE2017
/ - , 2017, 120-120
Skup
26th International Conference Nuclear Energy for New Europe NENE2017
Mjesto i datum
Bled, Slovenija, 11.09.2017. - 14.09.2017
Vrsta sudjelovanja
Poster
Vrsta recenzije
Međunarodna recenzija
Ključne riječi
NEK, RADTRAD, ORIGEN, source term
Sažetak
During severe accidents in the nuclear power plant it is possible to experience some fuel damage in the reactor core or within the Spent Fuel Pool (SFP). Radioactive elements released from fuel can reach the containment or Fuel Handling Building (FHB). In order to model transport of the radioactive material and to estimate dose to the people, the equipment and the environment, it is required to calculate activity and isotopic composition of the fuel (source term) and to group released isotopes according to their transport properties. The source term depends on initial amount of the fuel, its enrichment and acquired burnup. Taking into account number of isotopes and specific requirements imposed by the codes used for calculation of the radioactive materials transport that can be challenging task. The paper presents procedure for automatic preparation of radioactive inventory data (mass, activity) for severe accident (MAAP, MELCOR) or consequence calculation codes (RADTRAD) based on ORIGEN2 depletion calculation. The depletion is performed on assembly-by-assembly basis using power/burnup 3D data calculated by PARCS code and prescribed time vector for radioactive decay calculation. The source term data can be prepared for reactor core or for whole or part of SFP inventory. In SFP case information obtained from SFPFA spent fuel assembly management system is used. The calculations are performed for NPP Krsko core cycle 29 and current content of NPP Krsko SFP.
Izvorni jezik
Engleski
POVEZANOST RADA