T h e preliminary design o f a 3095-Mw(thermal), helium-cooled, graphite-moderated reactor employing graphite-U02 fuel elements has been investigated. At design conditions, 150OOF reactor outlet gas would be circulated t o eight steam generators to produce 1O5O0F, 1450-psi steam which would be converted to electrical power i n eight 157-Mw(electrica1) turbine-generators. The overall efficiency of t h i s nuclear power station i s 36.5%. The significant a c t i v i t i e s released from the unclad graphite-U02 fuel appear t o be less than 0.2% of those produced and would be equivalent to 0.002 curie/cm3 in the primary helium circuit. The maintenance problems associated with this contamination level are discussed. A cost analysis indicates that the capital cost o f this nuclear station per electrical k i l o w a t t would be around $220, and that the production cost o f electrical power would be 7.8 milIs/kwhr.
This report was prepared as an account d Government sponsored work. Neither the United Etatee, nor the Cormnission, nor any pereon acting on behalf d the Commlsrlon: A. Maker any warranty or representation, express or implied, with reepect to the accuracy, completeness, or usefulness d the lnformation contalned in thls report, or that the use of any Information, apparatus, method, or process disclosed in this report may not infringe privately owned rights; or B. Assumes any liabilitiee with respect to the use of, or for daamges resulting from the use of any Information, apparatus, method, or process disclosed in this report. As used in the above, "person acting on behalf d the Commission" includes any employee or contractor of the Commission to the extent that such employee or contractor prepares, handles or distributee, or provides access to, any lnformation pursuant to his employment or contract with the Commission.
The activity in the cooling water and in the demineralizer of the HMSR has been examined and reported in CF-58-5-83. This study established the fact that there were several uncertainties associated with predicting activity levels in water-cooled reactors. In order to evaluate these uncertainties, discussions were held with personnel at KAPL, ALCO Products, Combustion Engineering, and Ft. Belvoir.The topics discussed and covered in this memo are:Effect of in-pile and out-of-pile material on water activity buildup.
This repat was prepared as an o~counS of Govomarscrc sponsored work. Weirher th. United Stutee, not the Comdission, nor. on); poreom ocflng on b6half of the Commlssionr A. h k r s any wurrmty or reprbsentotion, expressed or impllud, wRh rropect t o tbr accufflcy. comp4rt.mrs, or usefulness of the iniarmation conmlned i n fhis reporf, or h a t fhe u r e of any inferination, oppmrotuc, method, or procass &isclosed in thh fupori may net infringe privately owned rights: or B. Aasumoc any Ilobillties with t e s p c t to the use of, or for domagn resulting from the use of any informbatio~, oppo?stur. method, or promess disclosed in this repMa As wed I n the above, "person acting on behalf of the Commis~ion'~ includes m y ehtployee or sonnacto, of the Commircfon, or employee of sweh centmotor, to the extent that sucrh e m~i o p e or contractor of the Commission, or employee of such contractor preporor, dimeminotea. or provides occess to, any information purswnt t o his employment oz contract with the CommissEon, or his employment with such controetar.
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