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Improved Core Design of a High Breeding Fast Reactor Cooled by Supercritical Pressure Light Water

[+] Author and Article Information
Sukarman Sukarman

Cooperative Major in Nuclear Energy, Graduate School of Advanced Science and Engineering, Waseda University, Nishi-Waseda Campus, 3-4-1, Okubo, Shinjuku-Ku, Tokyo, 169-8555, Japan
sukarman@asagi.waseda.jp

Akifumi Yamaji

Cooperative Major in Nuclear Energy, Graduate School of Advanced Science and Engineering, Waseda University, Nishi-Waseda Campus, 3-4-1, Okubo, Shinjuku-Ku, Tokyo, 169-8555, Japan
akifumi.yamaji@waseda.jp

Takayuki Someya

Cooperative Major in Nuclear Energy, Graduate School of Advanced Science and Engineering, Waseda University, Nishi-Waseda Campus, 3-4-1, Okubo, Shinjuku-Ku, Tokyo, 169-8555, Japan
russell@ruri.waseda.jp

1Corresponding author.

ASME doi:10.1115/1.4037719 History: Received April 18, 2017; Revised August 13, 2017

Abstract

There has not been an attractive light water reactor concept, which achieves high breeding performance with respect to the compound system doubling time (CSDT). In the preceding study, a high breeding fast reactor concept, cooled by supercritical pressure light water (Super FBR) was developed using tightly packed fuel assembly (TPFA) concept, in which fuel rods were arranged in a hexagonal lattice and packed by contacting each other. However, the designed concept had characteristics, which had to be improved, such as low power density (7.4 kW/m), large core pressure loss (1.02 MPa), low discharge burnup (core average: 8 GWd/tHM), low coolant temperature rise in the core (38 K). The aim of this study is to clarify the main issues associated with improvement of the Super FBR with respect to these design parameters and to show the improved design. The core design is carried out by fully-coupled three-dimensional neutronics and single channel thermal-hydraulics core calculations. The design criteria are negative void reactivity, maximum linear heat generation rate (MLHGR) of 39 kW/m, and maximum cladding surface temperature (MCST) of 650 C for advanced stainless steel. The results show that significant improvement is possible with respect to the core thermal-hydraulics characteristics with minimal deterioration of CSDT by replacing TPFA with TLFA. Further design studies are necessary to improve the core enthalpy rise by reducing the radial power swing and power peaking.

Copyright (c) 2017 by ASME
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