In-core fuel management strategy for the basket-fuel-assembly molten salt reactor
Creators
- 1. University of Chinese Academy of Sciences, Beijing (China)
- 2. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, Shanghai (China)
Description
Molten salt reactor, with good economics and inherent reliability, is one of the six types of Generation IV candidate reactors. The Basket-Fuel-Assembly Molten Salt Reactor (BFAMSR) is a new concept design based on fuel assemblies composed of fuel pebbles made of TRISOcoated particles. Four refueling patterns, similar to the fuel management strategy for water reactors, are designed and analyzed for BFAMSR in terms of economy and security. The MCNPX is employed to calculate the parameters, such as the total duration time, cycle length, discharge burnup, total discharge quantity of 235U, total discharge quantity of 239Pu, neutron flux distribution and power distribution. The in-out loading pattern has the highest burnup and duration time, the worst neutron flux and power distribution and the lowest neutron leakage. The out-in pattern possesses the most uniform neutron flux distribution, the lowest burnup and total duration time, and the highest neutron leakage.The out-in partition alternate pattern has slightly higher burnup, longer total duration time and smaller neutron leakage than that of the out-in loading pattern at the cost of sacrificing some neutron flux distribution and power distribution. However, its alternative distribution of fuel elements cut down the refueling time. The low-leakage pattern is the second highest in burnup, and total duration time, and its neutron flux and power distributions are the second most uniform. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Science and Techniques
- Journal Volume
- 28
- Journal Issue
- 9
- Journal Page Range
- [13 p.]
- ISSN
- 1001-8042
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 52016013
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP; DISTRIBUTION; FUEL ASSEMBLIES; FUEL ELEMENTS; FUEL MANAGEMENT; MOLTEN SALT REACTORS; NEUTRON FLUX; NEUTRON LEAKAGE; PLUTONIUM 239; POWER DISTRIBUTION; REACTOR CORES; RELIABILITY; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; EVEN-ODD NUCLEI; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MANAGEMENT; MINUTES LIVING RADIOISOTOPES; NUCLEAR MATERIALS MANAGEMENT; NUCLEI; PLUTONIUM ISOTOPES; RADIATION FLUX; RADIOISOTOPES; REACTOR COMPONENTS; REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 13 figs., 5 tabs., 21 refs.; http://dx.doi.org/10.1007/s41365-017-0286-8