Dynamic Analysis of the Next Generation Molten-Salt Breeder Reactor System
- 1. University of Tennessee, Department of Nuclear Engineering, Knoxville, TN 37996-2300 (United States)
Description
The conceptual design of a 1000 MWe two-fluid molten-salt breeder reactor (MSBR) station was performed during 1966-1970 at Oak Ridge National Laboratory (ORNL) with the goal of using the U-233 fuel cycle. This modular design with four reactor modules has an electrical output of 250 MW/module. The abundance of Th-232 was attractive in converting it to U-233 in a thermal breeder reactor. The two-fluid reactor is graphite-moderated 'with a 7LiF-BeF2-UF4 fuel salt circulated through the core and a 7LiF-ThF4-BeF2 blanket salt circulated through separate flow channels distributed throughout the core, as well as in a surrounding under-moderated region'. This reactor design has the advantages of not producing Pu isotopes and easy chemical separation of U-233 in the blanket material. The low fuel cost and the graphite replacement cost are attractive for such a design, with an estimated cost of $141/kW at 1968-dollar value. Potential non-proliferation features of MSBR, the low costs of raw materials, and established chemical separation of fission products are important factors in further development of MSBRs as an alternative to current light water reactors. These reactors are often referred to as liquid fluoride thorium reactor (LFTR). The current research on the modeling of the MSBR is based on an earlier work on the preliminary dynamic model of the MSBR concept. Revisions are made to the original model. The physics parameters have been modified for the current modeling effort based on additional information including more recent values of model parameters from and several typographical misprints in equations and values. Details of this effort will be presented in a full follow-up paper. This work presents the detailed nodal models of reactor fluid core, blanket fluid loop, graphite moderator, fuel fluid heat exchanger, and the blanket fluid heat exchanger. A set of simulations has been performed to validate the model using the commercial software MATLABTM-Simulink. Simulations were performed for the cases of source perturbation and reactivity perturbation. The model is inherently nonlinear. A description of the MSBR conceptual design, along with a tabulation of relevant system parameters, is presented. The results of simulation demonstrate stable behavior of the MSBR dynamics, temperature feedback effects, and load-following capability of the MSBR system
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 116
- Journal Page Range
- p. 1177-1180
- ISSN
- 0003-018X
Conference
- Title
- 2017 Annual Meeting of the American Nuclear Society
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52090735
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BERYLLIUM FLUORIDES; BREEDER REACTORS; COMPUTERIZED SIMULATION; FISSION PRODUCTS; GRAPHITE; HEAT EXCHANGERS; LIQUIDS; LITHIUM FLUORIDES; MOLTEN SALTS; ORNL; PERTURBATION THEORY; PLUTONIUM ISOTOPES; RAW MATERIALS; REACTOR DESIGN; THORIUM 232; THORIUM FLUORIDES; URANIUM 233; URANIUM TETRAFLUORIDE; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ALKALI METAL COMPOUNDS; ALKALINE EARTH METAL COMPOUNDS; ALPHA DECAY RADIOISOTOPES; BERYLLIUM COMPOUNDS; BERYLLIUM HALIDES; CARBON; DESIGN; ELEMENTS; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; FLUIDS; FLUORIDES; FLUORINE COMPOUNDS; HALIDES; HALOGEN COMPOUNDS; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; ISOTOPES; LITHIUM COMPOUNDS; LITHIUM HALIDES; MATERIALS; MINERALS; NATIONAL ORGANIZATIONS; NEON 24 DECAY RADIOISOTOPES; NONMETALS; NUCLEI; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTOR LIFE CYCLE; REACTORS; SALTS; SIMULATION; SPONTANEOUS FISSION RADIOISOTOPES; THORIUM COMPOUNDS; THORIUM HALIDES; THORIUM ISOTOPES; URANIUM COMPOUNDS; URANIUM FLUORIDES; URANIUM HALIDES; URANIUM ISOTOPES; US AEC; US DOE; US ERDA; US ORGANIZATIONS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 4 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)