Published 2006
| Version v1
Book
Neutron transport and diffusion models for molten-salt reactor dynamics
Creators
- 1. Politecnico di Torino (Italy)
- 2. CEA Saclay (France)
Description
The steady state and time dependent equations for a molten-salt reactor are numerically solved adopting the multigroup diffusion and transport models for neutrons. The motion of the multiplying material is properly accounted for in the balance equations for delayed neutron precursors. Non-linear feed-back phenomena are also taken into account by coupling the neutron equations with a simplified zero-dimensional thermal model. The analysis of the results presented allows the identification of physical situations for which transport effects can play an important role and thus must be properly described in the study of realistic system configurations. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-697-7
- Imprint Pagination
- 7 p.
Conference
- Title
- American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation
- Acronym
- PHYSOR-2006
- Dates
- 10-14 Sep 2006
- Place
- Vancouver, BC (Canada)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 43129895
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DELAYED NEUTRON PRECURSORS; MOLTEN SALT REACTORS; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT; NEUTRON TRANSPORT THEORY; NONLINEAR PROBLEMS; REACTOR KINETICS; STEADY-STATE CONDITIONS; TIME DEPENDENCE
- Descriptors DEC
- DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; EQUATIONS; ISOTOPES; KINETICS; NEUTRAL-PARTICLE TRANSPORT; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION TRANSPORT; RADIOISOTOPES; REACTORS; TRANSPORT THEORY
Optional Information
- Notes
- 4 refs.