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Fission-Product Release from UO2

Description: Release of fission products from UO2 with emphasis on fuel elements operated at higher surface temperatures and lower external pressures than those for pressurized-water systems.
Date: September 13, 1960
Creator: Cottrell, W. B.; Culver, H. N.; Scott, J. L. & Yarosh, M. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Study of Problems Associated With Release of Fission Products From Ceramic Fuels in Gas-Cooled Reactors

Description: The diffusion of fission products out of the fuel elements leads to increased shielding requirements, a greater hazard due to their possible release to the surroundings, and more difficult maintenance problems. Continuous processing of the contaminated coolant may alleviate the hazard and maintenance problems; however, extensive in-pile loop experiments are needed for a quantitative evaluation of methods. By proper design of major components such as heat exchangers and blowers, direct maintenan… more
Date: October 28, 1959
Creator: Lane, J. A.; Bennett, L. L.; Culver, H. N.; King, L. J.; Sanders, J. P.; Scott, J. L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE HGCR-1, A DESIGN STUDY OF A NUCLEAR POWER STATION EMPLOYING A HIGH- TEMPERATURE GAS-COOLED REACTOR WITH GRAPHITE-UO$sub 2$ FUEL ELEMENTS

Description: The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO/sub 2/ fuel appear to be less than 0.2% of thos… more
Date: July 28, 1959
Creator: Cottrell, W. B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements

Description: "The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO₂ fuel appear to be less than 0.2% of those pro… more
Date: 1959
Creator: Cottrell, William B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

TRIP TO ALCO PRODUCTS, KAPL, COMBUSTION ENGINEERING CO. AND FT. BELVOIR (APPR). RE: COOLING WATER ACTIVITY BUILDUP IN PRESSURIZED WATER REACTORS

Description: Several uncertainties associated with predicting activity levels in water-cooled reactors are discussed in connection with development of the Nuclear Merchant Ship Reactor (Maritime Pressurized Water Reactor). (T.R.H.)
Date: August 1, 1958
Creator: Culver, H.N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

GAS COOLED PEBBLE BED REACTOR FOR A LARGE CENTRAL STATION. Reactor Design and Feasibility Study

Description: An optimum econonic design for a high temperature, helium cooled, central station reactor power plant of about 400 Mw of electric power was determined. The core consists of a randomly packed bed of unclad graphite spheres, approximately one in. in diameter, impregnated with U/sup 233/ and thorium such that a conversion ratio of near unity is achieved. The high temperature helium permits steam conditions, at the turbine throttle, of 1000 deg F and 1450 psia. (auth)
Date: August 1, 1957
Creator: Schock, A.; Bruley, D.F.; Culver, H.N.; Ianni, P.W.; Kaufman, W.F.; Schmidt, R.A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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