Published 2006 | Version v1
Book

Neutron transport and diffusion models for molten-salt reactor dynamics

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)

Optional Information

Notes
4 refs.