Uncertainty analysis of transportable fluoride-salt-cooled high temperature reactor (TFHR)
- 1. Massachusetts Institute of Technology, Cambridge, Massachusetts (United States)
- 2. Xi'an Jiaotong University, Xi'an (China)
Description
The uncertainty and sensitivity quantification investigation of MIT proposed 20 MWth prismatic Transportable Fluoride-salt-cooled High Temperature Reactor (TFHR) is performed with the DAKOTA code coupled to the commercial nuclear best-estimate software RELAP5. Model input parameters were selected with specified variations and probability density functions, a total of 200 steady state calculations were then conducted in order to statistically determine 95% peak fuel temperature tolerance intervals with 95% confidence level. It was found that uncertainties in the heat transfer coefficient and helium gap were the most significant contributors to the propagated peak fuel temperature uncertainty. About 0.5% of calculated fuel temperatures exceeded the fuel damage. The current design of THFR needs further optimization from the prospective of thermal-hydraulics. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 38
- Journal Issue
- 3
- Journal Page Range
- p. 168-171
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 52062081
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CODES; DAMAGE; DESIGN; FLUORIDES; FUELS; HEAT TRANSFER; HELIUM; OPTIMIZATION; PEAKS; PROBABILITY DENSITY FUNCTIONS; SALTS; SENSITIVITY; STEADY-STATE CONDITIONS; TEMPERATURE RANGE 0400-1000 K; THERMAL HYDRAULICS; TOLERANCE; VARIATIONS
- Descriptors DEC
- ELEMENTS; ENERGY TRANSFER; FLUID MECHANICS; FLUIDS; FLUORINE COMPOUNDS; FUNCTIONS; GASES; HALIDES; HALOGEN COMPOUNDS; HYDRAULICS; MECHANICS; NONMETALS; RARE GASES; TEMPERATURE RANGE
Optional Information
- Notes
- 6 figs., 3 tabs., 7 refs.