Applicability of the Krško nuclear power plant core Monte Carlo model for the determination of the neutron source term
| Autor: | Domen Kotnik, Žiga Štancar, Marjan Kromar, Luka Snoj, Tanja Goričanec |
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| Jazyk: | angličtina |
| Rok vydání: | 2021 |
| Předmět: |
Physics
Neutron transport Nuclear engineering Monte Carlo neutron transport Monte Carlo method TK9001-9401 CORD-2 Krško nuclear power plant law.invention Core (optical fiber) Nuclear Energy and Engineering Nuclear reactor core law Nuclear power plant In-core neutron detector MCNP Neutron source Pressurized water reactor Nuclear engineering. Atomic power Core model Power density |
| Zdroj: | Nuclear Engineering and Technology, Vol 53, Iss 11, Pp 3528-3542 (2021) |
| ISSN: | 1738-5733 |
| Popis: | A detailed geometrical model of a Krško reactor core was developed using a Monte Carlo neutron transport code MCNP. The main goal of developing an MCNP core model is for it to be used in future research focused on ex-core calculations. A script called McCord was developed to generate MCNP input for an arbitrary fuel cycle configuration from the diffusion based core design package CORD-2, taking advantage of already available material and temperature data obtained in the nuclear core design process. The core model was used to calculate 3D power density profile inside the core. The applicability of the calculated power density distributions was tested by comparison to the CORD-2 calculations, which is regularly used for the nuclear core design calculation verification of the Krško core. For the hot zero power and hot full power states differences between MCNP and CORD-2 in the radial power density profile were |
| Databáze: | OpenAIRE |
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