Simulation of radiation dose distribution and thermal analysis for the bulk shielding of an optimized molten salt reactor
Creators
- 1. University of Chinese Academy of Sciences, Beijing (China)
- 2. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai (China)
- 3. Chengdu University of Technology, Chengdu (China)
Description
The Chinese Academy of Science has launched a thorium-based molten-salt reactor (TMSR) research project with a mission to research and develop a fission energy system of the fourth generation. The TMSR project intends to construct a liquid fuel molten-salt reactor (TMSR-LF), which uses fluoride salt as both the fuel and coolant, and a solid fuel molten-salt reactor (TMSR-SF), which uses fluoride salt as coolant and TRISO fuel. An optimized 2 MWth TMSR-LF has been designed to solve major technological challenges in the Th-U fuel cycle. Preliminary conceptual shielding design has also been performed to develop bulk shielding. In this study, the radiation dose and temperature distribution of the shielding bulk due to the core were simulated and analyzed by performing Monte Carlo simulations and computational fluid dynamics (CFD) analysis. The MCNP calculated dose rate and neutron and gamma spectra indicate that the total dose rate due to the core at the external surface of the concrete wall was 1.91 μSv/h in the radial direction, 1.16 μSv/h above and 1.33 μSv/h below the bulk shielding. All the radiation dose rates due to the core were below the design criteria. Thermal analysis results show that the temperature at the outermost surface of the bulk shielding was 333.86 K, which was below the required limit value. The results indicate that the designed bulk shielding satisfies the radiation shielding requirements for the 2 MWth TMSR-LF. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Science and Techniques
- Journal Volume
- 26
- Journal Issue
- 4
- Journal Page Range
- [6 p.]
- ISSN
- 1001-8042
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 49086574
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; DOSE RATES; ENERGY SYSTEMS; FISSION; FLUID MECHANICS; FLUORIDES; GAMMA SPECTRA; MOLTEN SALT REACTORS; MONTE CARLO METHOD; NEUTRONS; RADIATION DOSE DISTRIBUTIONS; RADIATION DOSES; SHIELDING; TEMPERATURE DISTRIBUTION; THERMAL ANALYSIS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; DOSES; ELEMENTARY PARTICLES; FERMIONS; FLUORINE COMPOUNDS; HADRONS; HALIDES; HALOGEN COMPOUNDS; MECHANICS; NUCLEAR REACTIONS; NUCLEONS; REACTORS; SIMULATION; SPECTRA
Optional Information
- Notes
- 6 figs., 1 tab., 21 refs.; http://dx.doi.org/10.13538/j.1001-8042/nst.26.040603