ANGRA-1 neutron kinetics model at BOL using WIMSD-5B and PARCS V2.7 codes
Creators
- 1. Universidade Federal de Minas Gerais (UFMG), Belo Horizonte (Brazil). Departamento de Engenheria Nuclear
- 2. Universitat Politecnica de Valencia (Spain)
Description
A steady-state neutron kinetics model of the Angra-1 NPP at BOL (Beginning Of Life) has been developed with the PARCS V2.7 neutron diffusion code. The information of the burnable poison rods, fuel enrichments and control rod banks distributions within the core have been taken from the Angra-1 FSAR (Final Safety Analysis Report) and implemented in the model. The macroscopic cross sections for the fast and thermal neutron groups have been calculated with the WIMSD-5B lattice cell code. The cross sections were obtained for the rodded and unrodded cases for each composition in the core. In order to establish the initial steady-state, an eigenvalue was made with the PARCS V2.7 code for three steady-state scenario cases reported at the FSAR; a Keff of 1.0733 was obtained for the unrodded case, Keff of 1.0718 for a 24% of bank D inserted case and Keff of 0.8512 for the full rodded case. The normalized core power density distributions were obtained and compared with the corresponding FSAR case. (author)
Files
46135080.pdf
Files
(1.2 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- INIS-BR--15657
Conference
- Title
- international nuclear atlantic conference. Brazilian nuclear program. State policy for a sustainable world; 19. ENFIR: meeting on nuclear reactor physics and thermal hydraulics
- Acronym
- INAC 2015
- Dates
- 4-9 Oct 2015
- Place
- Sao Paulo, SP (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 46135080
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANGRA-1 REACTOR; BURNABLE POISONS; COMPUTERIZED SIMULATION; CROSS SECTIONS; EIGENVALUES; FAST NEUTRONS; FUEL RODS; NEUTRON DIFFUSION EQUATION; P CODES; REACTOR CORES; REACTOR KINETICS; THERMAL NEUTRONS
- Descriptors DEC
- BARYONS; COMPUTER CODES; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EQUATIONS; FERMIONS; FUEL ELEMENTS; HADRONS; KINETICS; MATERIALS; NEUTRON ABSORBERS; NEUTRONS; NUCLEAR POISONS; NUCLEONS; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS