Published 2014
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Modeling and Simulation Monte Carlo by the MCNP code for determining neutron parameters of the nuclear reactor-subcritical assembly in CNSTN
Description
As part of developing its nuclear infrastructure base, the National Science and Technology Center Nuclear (CNSTN) examines the technical feasibility of setting up a new installation of subcritical assembly. Our study focuses on determining the neutron parameters of a nuclear zero power reactor based on Monte Carlo simulation MCNP. The objective of the simulation is to model the installation, determine the effective multiplication factor, and spatial distribution of neutron flux.
Availability note (English)
Also available from Faculte des Sciences de de Tunis, Tunisia (TN)Files
46051970.pdf
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Additional details
Additional titles
- Original title (French)
- Modelisation et simulation par le code Monte Carlo MCNP pour la determination des parametres neutroniques du reacteur- assemblage nucleaire sous-critique au CNSTN
Publishing Information
- Imprint Pagination
- 113 p.
- Report number
- INIS-TN--188
INIS
- Country of Publication
- Tunisia
- Country of Input or Organization
- Tunisia
- INIS RN
- 46051970
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- DISTRIBUTION; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NEUTRON FLUX; SIMULATION
- Descriptors DEC
- CALCULATION METHODS; DIMENSIONLESS NUMBERS; RADIATION FLUX
Optional Information
- Notes
- 19 refs.