A Sodium-Graphite Reactor Steam-Electric Station for 75 Megawatts Net Generation

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The major design features, nuclear characteristics and performance data for a nuclear fueled central station power plant of 75,000 kw net capacity are presented. The heat source is a Na cooled graphite moderated reactor. The design of the reactor takes full advantage of the experience gained to date on the Sodium Reactor Experiment (SRE); the plant described here is a straightforward extension of the smaller experimental SRE, which is now under construction. The fuel elements are made up of rod clusters and the moderator is in the form of Zr canned graphite elements. The performance of the reactor has been ... continued below

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Pages: 65

Creation Information

Weisner, E. F. & Sybert, W. M. March 22, 1955.

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Description

The major design features, nuclear characteristics and performance data for a nuclear fueled central station power plant of 75,000 kw net capacity are presented. The heat source is a Na cooled graphite moderated reactor. The design of the reactor takes full advantage of the experience gained to date on the Sodium Reactor Experiment (SRE); the plant described here is a straightforward extension of the smaller experimental SRE, which is now under construction. The fuel elements are made up of rod clusters and the moderator is in the form of Zr canned graphite elements. The performance of the reactor has been based on conservative temperatures and coolant flow velocities which result in a plant with "built-in reserve." Thus, as experience is gained and anticipated improvements in reactor fuel elements and construction materials are proven, the performance of the plant can be increased accordingly. Two reactor designs are described, one for operation with slightly enriched U fuel elements and the other for operation with Th--U fuel elements. The associated heat exchangers, pumps, steam, and electrical generating equipment are identical for either reactor design. An analysis of turbine cycles describes the particular cycle chosen for initial operation and discusses a method by which modern central station performance can be initially obtained. The design and performance data which are required to enable reliable estimates of the plant construction and operating costs to be made are established. (auth)

Physical Description

Pages: 65

Notes

NTIS

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  • Other Information: Decl. Feb. 28, 1957. Orig. Receipt Date: 31-DEC-58

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  • Report No.: NAA-SR-1300
  • Grant Number: AT(04-3)-49
  • DOI: 10.2172/4350785 | External Link
  • Office of Scientific & Technical Information Report Number: 4350785
  • Archival Resource Key: ark:/67531/metadc1027348

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • March 22, 1955

Added to The UNT Digital Library

  • Oct. 15, 2017, 10:09 p.m.

Description Last Updated

  • Jan. 22, 2018, 11:37 a.m.

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Weisner, E. F. & Sybert, W. M. A Sodium-Graphite Reactor Steam-Electric Station for 75 Megawatts Net Generation, report, March 22, 1955; Downey, California. (digital.library.unt.edu/ark:/67531/metadc1027348/: accessed October 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.