Coupling FHR core design with power conversion system
Creators
- 1. University of Cambridge, Department of Engineering, Trumpington Street, Cambridge, CB2 1PZ (United Kingdom)
Description
It has been suggested that the prismatic block type Fluoride-salt-cooled High temperature Reactors (FHRs) can benefit from Advanced Gas-cooled Reactors (AGRs) technologies. [1] This paper contributes to the global FHR development effort by investigating an AGR-like FHR concept. Two reference FHR assembly designs is proposed by replacing the CO2 coolant in a generic AGR with 2LiF-BeF2 (FLiBe), using UC and UO2 respectively. A model that couples the core thermal hydraulics design with the balance of plant design has been proposed in this study. Using the model, the optimum core coolant inlet and outlet temperatures, sizes and aspect ratios of the primary and secondary heat exchangers, pumping power required and temperature conditions of the heat transfer loops can be obtained for the proposed FHR designs. It is discovered in this study that the optimum reference core design using UC fuel is able to provide 3246 MWe with a coolant pressure loss of 490 kPa when operating at the same nominal condition as a generic AGR, increasing the AGR's power level by a factor of 4.9. (authors)
Additional details
Publishing Information
- Publisher
- Korean Nuclear Society - KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Pagination
- 10 p.
Conference
- Title
- International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering 2017
- Acronym
- M and C 2017
- Dates
- 16-20 Apr 2017
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- France
- INIS RN
- 53074572
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ASPECT RATIO; BERYLLIUM FLUORIDES; CARBON DIOXIDE; COOLANTS; COUPLING; FLIBE; GAS COOLED REACTORS; HEAT EXCHANGERS; HEAT TRANSFER; NUCLEAR FUELS; REACTOR DESIGN; THERMAL HYDRAULICS; URANIUM CARBIDES; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALKALINE EARTH METAL COMPOUNDS; BERYLLIUM COMPOUNDS; BERYLLIUM HALIDES; CARBIDES; CARBON COMPOUNDS; CARBON OXIDES; CHALCOGENIDES; DESIGN; DIMENSIONLESS NUMBERS; ENERGY SOURCES; ENERGY TRANSFER; FLUID MECHANICS; FLUORIDES; FLUORINE COMPOUNDS; FUELS; HALIDES; HALOGEN COMPOUNDS; HYDRAULICS; MATERIALS; MECHANICS; MOLTEN SALTS; OXIDES; OXYGEN COMPOUNDS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; SALTS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 14 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses