Analysis of Th-U breeding capability for an accelerator-driven subcritical molten salt reactor
- 1. Chinese Academy of Sciences, Shanghai Institute of Applied Physics (China)
Description
Accelerator-driven systems based on molten salt fuel have several unique advantages and features for advanced nuclear fuel utilization. The aim of this work was to study the Th-U breeding capability in such systems, known as "accelerator-driven subcritical molten salt reactors" (ADS–MSRs). Breeding capacities including conversion ratio and net production for various subcriticalities and different minor actinides (MA) loadings were analyzed for an ADS–MSR. The results show that the subcriticality of the core has a considerable effect on the Th-U breeding. A high subcriticality is favorable to improving the conversion ratio, increasing the net production, and reducing the doubling time. Specifically, the doubling time for of 0.99 is larger than 80 years, while the counterpart for of 0.93 is only approximately 22 years. Nevertheless, in an ADS–MSR with a high initial MA loading, MA results in a non-negligible depletion in the first two decades, while increasing the net production compared to reactors without MA loading. During the 50 years of operation, for the subcritical reactor () with MA fraction increasing from 1 to 14% , the net production increases from 3.94 to 8.24 t.
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Science and Techniques
- Journal Volume
- 29
- Journal Issue
- 8
- Journal Page Range
- p. 1-9
- ISSN
- 1001-8042
- CODEN
- NSETEC
INIS
- Country of Publication
- China
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50026397
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCELERATOR-DRIVEN SUBCRITICAL SYSTEMS; ACCELERATOR-DRIVEN TRANSMUTATION; BREEDING; CONVERSION RATIO; CRITICALITY; MOLTEN SALT FUELS; MOLTEN SALT REACTORS; REACTOR FUELING; THORIUM; URANIUM; URANIUM 233
- Descriptors DEC
- ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; DIMENSIONLESS NUMBERS; ELEMENTS; ENERGY SOURCES; EVEN-ODD NUCLEI; EXPERIMENTAL REACTORS; FUELS; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; ISOTOPES; LIQUID FUELS; MATERIALS; METALS; NEON 24 DECAY RADIOISOTOPES; NUCLEAR FUEL CONVERSION; NUCLEAR FUELS; NUCLEI; RADIOISOTOPES; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; SUBCRITICAL ASSEMBLIES; TRANSMUTATION; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2018 Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Chinese Nuclear Society, Science Press China and Springer Nature Singapore Pte Ltd.