AN ADVANCED SODIUM-GRAPHITE REACTOR NUCLEAR POWER PLANT

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Description

An advanced sodium-cooled, graphite-moderated nuclear power plant is described which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency. Steam is generated at 2400 psig, superheated to 1050 deg F and, after partial expansion in the turbine, reheated to 1000 deg F. Net thermal efficiency of the plant is 42.3%. In a plant sized to produce a net electrical output of 256 Mw, the estimated cost is 8232/kw. Estimated cost of power generation is 6.7 mills/kwh. In a similar plant with a net electrical output of 530 Mw, the estimated power generating cost is 5.4 mills/ kwh. ... continued below

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Pages: 162

Creation Information

Churchill, J. R. & Renard, J. March 15, 1960.

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Description

An advanced sodium-cooled, graphite-moderated nuclear power plant is described which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency. Steam is generated at 2400 psig, superheated to 1050 deg F and, after partial expansion in the turbine, reheated to 1000 deg F. Net thermal efficiency of the plant is 42.3%. In a plant sized to produce a net electrical output of 256 Mw, the estimated cost is 8232/kw. Estimated cost of power generation is 6.7 mills/kwh. In a similar plant with a net electrical output of 530 Mw, the estimated power generating cost is 5.4 mills/ kwh. Most of the components of the plant are within the capability of current technology. The major exception is the fuel material, uranium carbide. Preliminary results of the development work now in progress indicate that uranium carbide would be an excellent fuel for high-temperature reactors, but temperature and burnup limitation have yet to be firmly established. Additional development work is also required on the steam generators. These are the single-barrier type similar to those which will be used in the Enrico Fernri Fast Breeder Reactor plant but produce steam at higher pressure and temperature. Questions also remain regarding the use of nitrogen as a cover gas over sodium at 1200 deg F and compatibility of the materials used in the primary neutron shield. All of these questions are currently under investigation. (auth)

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Pages: 162

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  • Other Information: Orig. Receipt Date: 31-DEC-60

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  • Report No.: NAA-SR-3829
  • Grant Number: AT-11-1-GEN-8
  • DOI: 10.2172/4156655 | External Link
  • Office of Scientific & Technical Information Report Number: 4156655
  • Archival Resource Key: ark:/67531/metadc869251

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  • March 15, 1960

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  • Sept. 16, 2016, 12:32 a.m.

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  • Dec. 2, 2016, 7:12 p.m.

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Churchill, J. R. & Renard, J. AN ADVANCED SODIUM-GRAPHITE REACTOR NUCLEAR POWER PLANT, report, March 15, 1960; Canoga Park, California. (digital.library.unt.edu/ark:/67531/metadc869251/: accessed September 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.