Development of a dynamics model for graphite-moderated channel-type molten salt reactor
- 1. Chinese Academy of Sciences, Shanghai Institute of Applied Physics (China)
Description
A molten salt reactor (MSR) is one of the six advanced reactor concepts selected by the generation IV international forum because of its advantages of inherent safety, and the promising capabilities of Th-U breeding and transuranics transmutation. A dynamics model for the channel-type MSR is developed in this work based on a three-dimensional thermal–hydraulic model (3DTH) and a point reactor model. The 3DTH couples a three-dimensional heat conduction model and a one-dimensional single-phase flow model that can accurately consider the heat conduction between different assemblies. The 3DTH is validated by the RELAP5 code in terms of the temperature and mass flow distribution calculation. A point reactor model considering the drift of delayed neutron precursors is adopted in the dynamics model. To verify the dynamics model, three experiments from the molten salt reactor experiment are simulated. The agreement of the experimental data and simulation results was excellent. With the aid of this model, the unprotected step reactivity addition and unprotected loss of flow of the 2 MWt experimental MSR are modeled, and the reactor power and temperature evolution are analyzed.
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Science and Techniques
- Journal Volume
- 30
- Journal Issue
- 1
- Journal Page Range
- p. 1-11
- ISSN
- 1001-8042
- CODEN
- NSETEC
INIS
- Country of Publication
- China
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51082090
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BREEDING; COMPUTER CODES; DELAYED NEUTRON PRECURSORS; EXPERIMENTAL DATA; FLOW MODELS; GRAPHITE; LOSS OF FLOW; MASS DISTRIBUTION; MOLTEN SALT REACTORS; TEMPERATURE DISTRIBUTION; THERMAL CONDUCTION; THERMAL HYDRAULICS; THORIUM; THREE-DIMENSIONAL CALCULATIONS; TRANSMUTATION; TRANSURANIUM ELEMENTS; URANIUM
- Descriptors DEC
- ACCIDENTS; ACTINIDES; CARBON; DATA; DISTRIBUTION; ELEMENTS; ENERGY TRANSFER; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; INFORMATION; ISOTOPES; MATHEMATICAL MODELS; MECHANICS; METALS; MINERALS; NONMETALS; NUCLEAR FUEL CONVERSION; NUMERICAL DATA; RADIOISOTOPES; REACTOR ACCIDENTS; REACTORS; SPATIAL DISTRIBUTION
Optional Information
- Copyright
- Copyright (c) 2019 China Science Publishing & Media Ltd. (Science Press), Shanghai Institute of Applied Physics, the Chinese Academy of Sciences, Chinese Nuclear Society and Springer Nature Singapore Pte Ltd.