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Title: AN ADVANCED SODIUM-GRAPHITE REACTOR NUCLEAR POWER PLANT

Abstract

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 ofmore » 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)« less

Authors:
;
Publication Date:
Research Org.:
Atomics International Div., North American Aviation, Inc., Canoga Park, Calif.
Sponsoring Org.:
USDOE
OSTI Identifier:
4156655
Report Number(s):
NAA-SR-3829
NSA Number:
NSA-14-015456
DOE Contract Number:
AT-11-1-GEN-8
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; BURNUP; CHEMICAL REACTIONS; ECONOMICS; EFFICIENCY; GENERATORS; GRAPHITE MODERATOR; HIGH TEMPERATURE; LIQUID METAL COOLANT; NITROGEN; POWER; POWER PLANTS; PRESSURE; REACTORS; SODIUM; STEAM; SUPERHEATING; URANIUM CARBIDES

Citation Formats

Churchill, J.R., and Renard, J. AN ADVANCED SODIUM-GRAPHITE REACTOR NUCLEAR POWER PLANT. United States: N. p., 1960. Web. doi:10.2172/4156655.
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Churchill, J.R., & Renard, J. AN ADVANCED SODIUM-GRAPHITE REACTOR NUCLEAR POWER PLANT. United States. doi:10.2172/4156655.
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Churchill, J.R., and Renard, J. Tue . "AN ADVANCED SODIUM-GRAPHITE REACTOR NUCLEAR POWER PLANT". United States. doi:10.2172/4156655. https://www.osti.gov/servlets/purl/4156655.
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@article{osti_4156655,
title = {AN ADVANCED SODIUM-GRAPHITE REACTOR NUCLEAR POWER PLANT},
author = {Churchill, J.R. and Renard, J.},
abstractNote = {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)},
doi = {10.2172/4156655},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Mar 15 00:00:00 EST 1960},
month = {Tue Mar 15 00:00:00 EST 1960}
}
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Technical Report:
View Technical Report (7.22 MB)
DOI:  10.2172/4156655
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  • The conceptual design of a 100 Mw(e) nuclear power plant is described. The plant utilized a sodium-cooled graphite-moderated reactor with stainless- steel clad. slightiy enriched UO/sub 2/ fuel. The reactor is provided with three main coolant circuits, and the steam cycle has three stages of regenerative heating. The plant control system allows automatic operation over the range of 20 to 100% load, or manual operation at all loads. The site, reactor, sodium systems, reactor auxiliaries, fuel handling, instrumentation, turbine-generator, buildings. and safety measures are described. Engineering drawings are included. (W.D.M.)

  • ; ; ; ...
    The plant arrangement, component design, and the functions of various systems are described and illustrated. Relative estimated costs of the systems and major components are indicated. The reactor core is designed around requiremouts for 254 thermal megawatts, 950 deg F maximum sodium temperature, stainless steel clad graphite moderator blocks, and low enrichment (0.015 to 0.04 U/sup 235/) uranium fuel elements. The fuel cycle is described for the possible fuel elements. The fuel cost factors are discussed. Burn-up limitations encountered for metallic fuel in the SGR temperature range indicate UO/sub 2/ the more desirable choice. The estimated cost of electrical energymore » associated with the UO/sub 2/ fuel is given. (auth)« less

  • ; ; ; ...
    A description is given of the Advanced Sodium Graphite Reactor Power Plant, including the reactor, heat transfer systems, generatirg plant, control systems, and the economics of producing 256 Mw(e). The safety of this design is due to its unusually low operating pressure, absence of chemically incompatible materials in the core, and excellent stability under atatic and dynamic conditions. The reactor is being constructed at Hallam, Nebraska, at a probable cost of 0 to 0/kw, exclusive of the first core costs. The 151 fuel elements of uranium carbide are enriched to 2.75 at.% U/sup 235/ and clad in stainless steel. Themore » average thermal neutron flux in the fuel is 8 x 10/sup 13/ n/cm/sup 2/sec. (B.O.G.)« less

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