Study for requirement of advanced long life small modular fast reactor

To develop an advanced long-life SMR core concept, the feasibility of the long-life breed-and-burn core concept has been assessed and the preliminary selection on the reactor design requirement such as fuel form, coolant material has been performed. With the simplified cigar-type geometry of 8m-tall...

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Bibliographic Details
Main Authors: Tak, Taewoo, Choe, Jiwon, Jeong, Yongjin, Lee, Deokjung, Kim, T. K.
Format: Conference Proceeding
Language:English
Subjects:
Absorption cross sections
BOILING POINTS
BREEDING
COOLANTS
Fast nuclear reactors
FAST REACTORS
Feasibility studies
MELTING POINTS
Nuclear fuels
NUCLEAR POWER PLANTS
Reactor design
SPECIFIC HEAT
SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
THERMAL CONDUCTIVITY
VISCOSITY
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Summary:To develop an advanced long-life SMR core concept, the feasibility of the long-life breed-and-burn core concept has been assessed and the preliminary selection on the reactor design requirement such as fuel form, coolant material has been performed. With the simplified cigar-type geometry of 8m-tall CANDLE reactor concept, it has demonstrated the strengths of breed-and-burn strategy. There is a saturation region in the graph for the multiplication factors, which means that a steady breeding is being proceeded along the axial direction. The propagation behavior of the CANDLE core can be also confirmed through the evolution of the axial power profile. Coolant material is expected to have low melting point, density, viscosity and absorption cross section and a high boiling point, specific heat, and thermal conductivity. In this respect, sodium is preferable material for a coolant of this nuclear power plant system. The metallic fuel has harder spectrum compared to the oxide and carbide fuel, which is favorable to increase the breeding and extend the cycle length.
ISSN:0094-243X
1551-7616
DOI:10.1063/1.4940059