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Massachusetts Institute of Technology

A supercritical carbon dioxide cycle for next generation nuclear reactors

Abstract

dc:description.abstract

A systematic, detailed major component and system design evaluation and multiple parameter optimization under practical constraints has been performed of the family of supercritical CO2 Brayton power cycles for application to advanced nuclear reactors. The recompression cycle is shown to excel with respect to simplicity, compactness, cost and thermal efficiency. The main advantage of the supercritical CO2 cycle is comparable efficiency with the helium Brayton cycle at significantly lower temperature (550⁰C vs. 850 ⁰C), but higher pressure (20 MPa vs. 8 MPa). The supercritical CO2 cycle is well suited to any type of nuclear reactor with core outlet temperature above [approx.] 500 ⁰C in either direct or indirect versions. By taking advantage of the abrupt property changes near the critical point of CO2 the compression work can be reduced, which results in a significant efficiency improvement. However, a real gas cycle requires much more careful optimization than an ideal gas Brayton cycle. Previous investigations by earlier authors were systematized and refined in the present work to survey several different CO2 cycle layouts. Inter- cooling, re-heating, re-compressing and pre-compressing were considered. The recompression cycle was found to yield the highest efficiency, while still retaining simplicity. Inter-cooling is not attractive for this type of cycle as it offers a very modest efficiency improvement. Re-heating has a better potential, but it is applicable only to indirect cycles. Economic analysis of the benefit of re-heating for the indirect cycle showed that using more than one stage of re-heat is economically unattractive.

Degree

thesis:*
Department dc:contributor.department
Massachusetts Institute of Technology. Department of Nuclear Engineering
Grantor dc:publisher
Massachusetts Institute of Technology
Year dc:date.issued
2004

Author and committee

dc:creator, dc:contributor.*
Author dc:creator
  • Dostal, Vaclav, 1976-
Advisor dc:contributor.advisor
  • Michael J. Driscoll.

Subjects

dc:subject × 1

Rights

dc:rights
Statement dc:rights
  • M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission.
Language dc:language.iso
eng

Identifiers

dc:identifier.*
Handle dc:identifier.uri
http://hdl.handle.net/1721.1/17746
OAI identifier oai:identifier
oai:dspace.mit.edu:1721.1/17746

Chain of custody

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MIT
Base URL
dspace.mit.edu/oai/request
Last updated
2026-07-22
Source record
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related terms
citation

Dostal, Vaclav, 1976-. A supercritical carbon dioxide cycle for next generation nuclear reactors. Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/17746