Steam-cooled Power Reactor Evaluation
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Published: 1960
Total Pages: 200
ISBN-13:
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Author:
Publisher:
Published: 1960
Total Pages: 200
ISBN-13:
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Published: 1973
Total Pages: 1132
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Published: 1962
Total Pages: 1990
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DOWNLOAD EBOOKAuthor: G. V. Brynsvold
Publisher:
Published: 1962
Total Pages: 276
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DOWNLOAD EBOOK"This report presents the conceptual design of a 75 MWe prototype Mixed Spectrum Superheater power plant. The scope of the work has emphasized primarily the design, performance, and cost information on the nuclear portion of the plant. The research and development programs required to insure plant feasibility are also present."--Intro.
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Publisher:
Published: 1959
Total Pages: 770
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DOWNLOAD EBOOKAuthor: United States. Superintendent of Documents
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Published: 1980
Total Pages: 1284
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DOWNLOAD EBOOKAuthor: United States. Superintendent of Documents
Publisher:
Published: 1961
Total Pages: 1284
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DOWNLOAD EBOOKAuthor:
Publisher:
Published: 1962
Total Pages: 1166
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DOWNLOAD EBOOKAuthor: D. H. Lennox
Publisher:
Published: 1961
Total Pages: 78
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DOWNLOAD EBOOKVarious reactor concepts were compared for use as a separate superheater which could be added on to an advanced 300-Mwe reactor producing saturated steam. Fossil steam plant superheat temperatures were used as a criterion for selecting nuclear superheat temperatures. Therefore, the performance specified for the superheater was a minimum exit steam temperature of 566 deg C (1050 deg F) when supplied with saturated steam at either 71 atm (1050 psia) or 167 atm (2450 psia). A preliminary screening of ten different reactor concepts resulted in the selection of two for a detailed evaluation. These are a direct-cycle, water-moderated reactor, and an indirect-cycle, sodium-cooled reactor. The steam- cooled, water-moderated system is judged to have the best chance for initially reaching 566 deg C (l050 deg F), whereas, the indirect-cycle, sodium-cooled system is considered best for subsequent advances to exploit the more efficient, high- pressure steam reheat cycles. A design concept was selected for each of the reactors to establish a basis for the detailed evaluations and comparisons.