Pregled bibliografske jedinice broj: 1145898
Analysis of the HI-TRAC VW Transfer Cask Dose Rates During Nuclear Power Plant Krsko Spent Fuel Dry Storage Campaign One
Analysis of the HI-TRAC VW Transfer Cask Dose Rates During Nuclear Power Plant Krsko Spent Fuel Dry Storage Campaign One // Journal of Nuclear Engineering and Radiation Science, 8 (2021), 4; 041902, 8 doi:10.1115/1.4051447 (međunarodna recenzija, članak, znanstveni)
CROSBI ID: 1145898 Za ispravke kontaktirajte CROSBI podršku putem web obrasca
Naslov
Analysis of the HI-TRAC VW Transfer Cask Dose
Rates During Nuclear Power Plant Krsko Spent
Fuel Dry Storage Campaign One
Autori
Grgić, Davor ; Matijević, Mario ; Dučkić, Paulina ; Ječmenica, Radomir
Izvornik
Journal of Nuclear Engineering and Radiation Science (2332-8975) 8
(2021), 4;
041902, 8
Vrsta, podvrsta i kategorija rada
Radovi u časopisima, članak, znanstveni
Ključne riječi
spent fuel dry storage ; transfer cask ; radiation shielding ; MPNP6
Sažetak
In this paper shielding analysis was performed to determine neutron and gamma dose rates around the transfer cask HI-TRAC VW loaded with Spent Fuel Assemblies (SFA) from Nuclear Power Plant (NPP) Krsko Spent Fuel Dry Storage (SFDS) Campaign one. The HI-TRAC VW is a multi-layered cylindrical vessel designed to accept a Multi Purpose Canister (MPC) during loading, unloading and transfer to dry storage building. The MPC can contain up to 37 spent fuel assemblies. The analysis was divided into two steps. The first step was the source term generation using ORIGEN-S module of the SCALE code package. The source was calculated based on the operating history of spent fuel assemblies currently located in the NPP Krsko spent fuel pool. The obtained particle intensities and source spectra of the SFA were used in the second step to calculate the dose rates around the transfer cask. A comprehensive hybrid shielding analysis included the calculation of dose rates resulting from fuel neutrons and gammas, neutron induced gammas (n- g reaction), and hardware activation gammas under normal conditions and during accident scenario. To obtain the dose rates within the acceptable uncertainties, FW-CADIS variance reduction scheme, as implemented in ADVANTG code, was adopted for accelerating final MCNP6 calculations. The dose rates around HI-TRAC VW cask were calculated using MCNP6 code for all 16 casks loading belonging to Campaign one in order to illustrate the impact of fuel assembly selection schemes proposed by company responsible for project realization (Holtec International).
Izvorni jezik
Engleski
Znanstvena područja
Elektrotehnika
POVEZANOST RADA
Ustanove:
Fakultet elektrotehnike i računarstva, Zagreb
Profili:
Mario Matijević
(autor)
Radomir Ječmenica
(autor)
Paulina Dučkić
(autor)
Davor Grgić
(autor)
Citiraj ovu publikaciju:
Časopis indeksira:
- Web of Science Core Collection (WoSCC)
- Emerging Sources Citation Index (ESCI)
- Scopus