Published April 2017 | Version v1
Book

Coupling FHR core design with power conversion system

  • 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)

Optional Information

Notes
14 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses