Safety analysis on Brazilian multipurpose reactor using the RELAP5-3D code
Creators
- 1. Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares lnovadores/CNPq (Brazil)
- 2. Departamento de Engenharia Nuclear, Universidade Federal de Minas Gerais, Av. Antdnio Carlos, 6627 - PCA1 - Anexo Engenharia - Pampulha, CEP 31270-901 Belo Horizonte, MG, (Brazil)
- 3. Centro de Desenvo/vimento da Tecnologia Nuclear/Comissão Nacional de Energia Nuclear-CDTN/CNEN, Av. Antônio Carlos, 6627, CEP 31270-901 Campus UFMG, Belo Horizonte (Brazil)
Description
The Brazilian Multipurpose Reactor (Reator Multipropósito Brasileiro - RMB) is currently being projected and several analyses are being performed. It will be a 30 MW open pool multipurpose research reactor with a compact core using Materials Testing Reactor (MTR) fuel assembly with planar plates. RMB will be cooled by light water and moderated by beryllium and heavy water. This work presents the thermal hydraulic calculations of steady state operation of the RMB using a RELAP5 model and also a model of core using the multi- dimensional kinetic model in RELAP5-3D and PARCS code. The cross section was generated in the WlMSD-5B lattice code. The axial and radial relative power on the core was compared with three-dimensional CITATION diffusion code. The results showed good agreement with the reference. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- European Nuclear Society
- Imprint Place
- Brussels (Belgium)
- ISBN
- 978-92-95064-23-2
- Imprint Title
- European Research Reactor Conference (RRFM) 2015: Conference Proceedings
- Imprint Pagination
- 667 p.
- Journal Page Range
- p. 291-300
- Report number
- INIS-BE--16M5628
Conference
- Title
- 19. international topical meeting on Research Reactor Fuel Management (RRFM)
- Acronym
- RRFM 2015
- Dates
- 19-23 Apr 2015
- Place
- Bucharest (Romania)
INIS
- Country of Publication
- Belgium
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 47116429
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BERYLLIUM; BRAZIL; COMPARATIVE EVALUATIONS; COMPUTER CODES; CROSS SECTIONS; FUEL ASSEMBLIES; HEAVY WATER; MATERIALS TESTING REACTORS; REACTOR KINETICS; RESEARCH REACTORS; SAFETY ANALYSIS; STEADY-STATE CONDITIONS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ALKALINE EARTH METALS; DEUTERIUM COMPOUNDS; DEVELOPING COUNTRIES; ELEMENTS; EVALUATION; FLUID MECHANICS; HYDRAULICS; HYDROGEN COMPOUNDS; IRRADIATION REACTORS; KINETICS; LATIN AMERICA; MECHANICS; METALS; OXYGEN COMPOUNDS; REACTORS; RESEARCH AND TEST REACTORS; SOUTH AMERICA; WATER
Optional Information
- Notes
- © European Nuclear Society, 2003; 8 refs., 7 figs., 6 tabs.
- Secondary number(s)
- RRFM2015--A0055