Published 2007
| Version v1
Miscellaneous
A simulation of GM-MSR reactor using the MCNP and WIMSD5
Creators
- 1. Universidade do Estado de Minas Gerais, Belo Horizonte, MG (Brazil)
Description
The aim of this study is to evaluate the possibility of using the GM-MSR (Graphite Moderated-Molten Salt Reactor) like Pu and MAs (Minor Actinides) burner. It was simulated three fuels, using MCNP and WIMS code: a traditional combination of thorium and enriched uranium, a plutonium matrix come from PWR, replacing the uranium, and a matrix of plutonium and MAs, come from PWR too, replacing the uranium, keeping the enrichment and total volume in all substitutions. Some neutronic parameters were analyzed. (author)
Additional details
Publishing Information
- ISBN
- 978-85-99141-02-1
- Imprint Title
- Proceedings of the INAC 2007 International nuclear atlantic conference. Nuclear energy and energetic challenges for 21st. century. 15. Brazilian national meeting on reactor physics and thermal hydraulics; 8. Brazilian national meeting on nuclear applications
- Imprint Pagination
- [vp.]
- Journal Page Range
- [6 p.]
Conference
- Title
- INAC 2007 International nuclear atlantic conference. Nuclear energy and energetic challenges for 21st. century. 15. Brazilian national meeting on reactor physics and thermal hydraulics; 8. Brazilian national meeting on nuclear applications
- Dates
- 30 Sep - 5 Oct 2007
- Place
- Santos, SP (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 39093837
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; EXPERIMENTAL DATA; GRAPHITE; M CODES; MOLTEN SALT REACTORS; MONTE CARLO METHOD; MULTIPLICATION FACTORS; PLUTONIUM; TEMPERATURE DEPENDENCE; URANIUM; W CODES
- Descriptors DEC
- ACTINIDES; CALCULATION METHODS; CARBON; COMPUTER CODES; DATA; DIMENSIONLESS NUMBERS; ELEMENTS; INFORMATION; METALS; MINERALS; NONMETALS; NUMERICAL DATA; REACTORS; SIMULATION; TRANSURANIUM ELEMENTS
Optional Information
- Notes
- 1 ref., 4 figs., 1 tab. Code: R12_1693.pdf