Technology Selection for Offshore Underwater Small Modular Reactors
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Author(s) • • • • •
Shirvan, Koroush
Buongiorno, Jacopo
Forsberg, Charles W
Kazimi, Mujid S
Todreas, Neil E
Ballinger, Ronald G.
Date Issued
June 2016
Journal
Nuclear Engineering and Technology
Publisher
Elsevier BV
Citation
Shirvan, Koroush, Ronald Ballinger, Jacopo Buongiorno, Charles Forsberg, Mujid Kazimi, and Neil Todreas. “Technology Selection for Offshore Underwater Small Modular Reactors.” Nuclear Engineering and Technology 48, no. 6 (December 2016): 1303–1314.
Version
Final published version
Abstract
This work examines the most viable nuclear technology options for future underwater designs that would meet high safety standards as well as good economic potential, for construction in the 2030–2040 timeframe. The top five concepts selected from a survey of 13 nuclear technologies were compared to a small modular pressurized water reactor (PWR) designed with a conventional layout. In order of smallest to largest primary system size where the reactor and all safety systems are contained, the top five designs were: (1) a lead–bismuth fast reactor based on the Russian SVBR-100; (2) a novel organic cooled reactor; (3) an innovative superheated water reactor; (4) a boiling water reactor based on Toshiba's LSBWR; and (5) an integral PWR featuring compact steam generators. A similar study on potential attractive power cycles was also performed. A condensing and recompression supercritical CO2cycle and a compact steam Rankine cycle were designed. It was found that the hull size required by the reactor, safety systems and power cycle can be significantly reduced (50–80%) with the top five designs compared to the conventional PWR. Based on the qualitative economic consideration, the organic cooled reactor and boiling water reactor designs are expected to be the most cost effective options.
MIT Department
Massachusetts Institute of Technology. Department of Materials Science and Engineering
Massachusetts Institute of Technology. Department of Mechanical Engineering
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
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Creative Commons Attribution-NonCommercial-NoDerivs License
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DOI of Published Version
https://doi.org/10.1016/J.NET.2016.06.002