Numerical analysis for a molten salt reactor in the presence of localized perturbations
Creators
- 1. State Key laboratory of Multiphase Flow in Power Engineering, Department of Nuclear Science and Technology, Xi'an Jiaotong University, No. 28, Xianning West Road, Xi'an 710049 (China)
Description
Molten salt reactors (MSRs) have seen a marked resurgence of interest over the past few decades, highlighted by their inclusion as one of the six Generation IV reactor types. The MSRs are characterized by using the fluid-fuel, so that their technologies are fundamentally different from those used in the conventional solid-fuel reactors. In this paper, the attention is focused on the behaviors of an MSR in the presence of localized perturbations caused by fissile precipitates and gas bubbles. A neutron kinetic model considering the fuel salt flow is established based on the neutron diffusion theory, which consists of two-group neutron diffusion equations for the fast and thermal neutron fluxes and six-group balance equations for delayed neutron precursors, and the group constants dependent on the temperature are calculated by the code DRAGON. In addition, the k-epsilon turbulent model is adopted to establish the flow and heat transfer. The thermo-hydraulic and neutronic models are coupled through the temperature, heat source and velocity. The effects of the localized perturbation on the distributions of power, temperature, neutron fluxes and delayed neutron precursors are obtained and discussed in detail. The results provide some valuable information for the research and design of this new generation reactor.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.pnucene.2012.05.005Additional details
Identifiers
- DOI
- 10.1016/j.pnucene.2012.05.005;
- PII
- S014919701200073X;
Publishing Information
- Journal Title
- Progress in Nuclear Energy
- Journal Volume
- 60
- Journal Page Range
- p. 61-72
- ISSN
- 0149-1970
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51010979
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DELAYED NEUTRON PRECURSORS; DISTURBANCES; GROUP CONSTANTS; HEAT SOURCES; HEAT TRANSFER; MOLTEN SALT REACTORS; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NUMERICAL ANALYSIS; POWER DISTRIBUTION; REACTOR DESIGN; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS; THERMAL NEUTRONS
- Descriptors DEC
- BARYONS; CROSS SECTIONS; DESIGN; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ELEMENTARY PARTICLES; ENERGY TRANSFER; EQUATIONS; FERMIONS; FLUID MECHANICS; HADRONS; HYDRAULICS; ISOTOPES; MATHEMATICS; MECHANICS; NEUTRONS; NUCLEONS; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION FLUX; RADIOISOTOPES; REACTOR LIFE CYCLE; REACTORS
Optional Information
- Notes
- Copyright © 2012 Elsevier Ltd. All rights reserved.