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Compatibility of uranium-plutonium carbide fuels and potential LMFBR cladding materials

Description: The contact compatibility (in the absence of sodium) between (U,Pu)C with equivalent carbon contents of 4.83, 5.25, and 6.75 wt % and iron-, nickel- and vanadium-base alloys was studied at 700-1100{deg}C for 168-4000 hr. Austenitic iron-base alloys, containing 25 wt % or less nickel and tested at 800{deg}C for up to 4000 hr, showed little or no evidence of carbon transfer from stoichiometric or hyperstoichiometric (U{sub 0.8}Pu{sub 0.2})C that contained up to 20 vol % (U,Pu){sub 2}C{sub 3}. Thr… more
Date: September 1, 1971
Creator: Latimer, T W
Partner: UNT Libraries Government Documents Department
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Design, Fabrication, and Testing of an External-Fuel [UO2] Full-Length Thermionic Converter

Description: The development of a double-ended full-core-length external-fuel converter, a prototypical fuel module for a 200- to 300-ekw thermionic reactor, is described. The converter design is based on a revolver-shaped tungsten emitter body, with six peripheral fuel chambers loaded with enriched UO2 pellets. The columbium collector is water-cooled through a sub-atmospheric adjustable-pressure helium gap. The converter employs graded metal-ceramic seals, and its double-ended construction is made possible… more
Date: September 1, 1971
Creator: Schock, Alfred & Raab, B.
Partner: UNT Libraries Government Documents Department
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LMFBR (LIQUID METAL FAST BREEDER REACTOR) REACTION RATE AND DOSIMETRY QUARTERLY PROGRESS REPORT JUNE JULY AUGUST 1971

Description: This report describes progress in the USAEC-sponsored Interlaboratory LMFBR Reaction Rate (ILRR) program. This program has been established by RDT to develop a capability to accurately measure neutron-induced reaction rates for LMFBR fuels and materials development programs. The initial goal for the principal fission reactions, {sup 235}U, {sup 238}U, and {sup 239}Pu, is an accuracy to within {+-} 5 at the 95% confidence level. Accurate measurement of other fission and non-fission reactions wil… more
Date: September 1, 1971
Creator: WN, MCELROY
Partner: UNT Libraries Government Documents Department
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SAFETY ANALYSIS REPORT- BIOLOGY LABORATORIES PLUTONIUM - 238 EXPERIMENTS

Description: Fifty-watt, triply encapsulated radiation sources, supplied by the Division of Isotopes Development, AEC, and consisting of about 125 g of {sup 238}PuO{sub 2}{sup 16} (87.8 g of {sup 238}Pu in 110.2 g of Pu mixture, total activity 1500 Ci), are to be used in studies of the biologic effects of heat and radiation in support of the artificial heart program, under sponsorship of the Division of Biology and Medicine, AEC. A review of the circumstances which could lead to a loss of control of this mo… more
Date: September 1, 1971
Creator: Cross, F. T. & Gillis, M F.
Partner: UNT Libraries Government Documents Department
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A study of polyether-polyol- and polyester-polyol-based rigid urethane foam systems

Description: For the past 10 years polyurethane polymers have been one of the fastest growing segments of the plastics industry. Over 900 million pounds of polyurethanes were used in 1970. Approximately 30% of this amount was consumed in the form of rigid urethane foam products. This study undertakes a comparison of the properties of rigid urethane foams based on both a polyester polyol and polyether polyol of the same hydroxyl number prepared from alpha methylglucoside. This comparison of ester and ether p… more
Date: September 1, 1971
Creator: Madden, J. P.; Baker, G. K. & Smith, C. H.
Partner: UNT Libraries Government Documents Department
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Summary of Roswell Test Bed Plant Reports (1963-1968)

Description: From Summary: "This report summarizes the analyses of the operating data for the period 1963-1969 for the Test Bed Plant and the Auxiliary Test Unit (ATU) located at Roswell, New Mexico."
Date: September 1971
Creator: Phillips Scientific Corporation
Partner: UNT Libraries Government Documents Department
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Thermal stability of LX-09 chemical reactivity testing. Final report

Description: Several CRT tests were performed with LX-09 using sample containers obtained from LLL. These containers were used to help eliminate differences that were inherent in the design of the various sample containers used by the different laboratories. Initial experiments showed poor agreement in test data between LLL and Pantex containers until Pantex containers were fitted with different valves. Later experiments show no significant differences in test data between the two types of containers after … more
Date: September 1, 1971
Creator: Teter, A.C.
Partner: UNT Libraries Government Documents Department
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TGD weekly status report

Description: Activities described in the TGD weekly activities report include: completion of device radiography; a mandrel run completed; downhole stereo photographs of emplacement casing; and installment of x-ray detectors.
Date: September 4, 1971
Creator: Coyle, P.
Partner: UNT Libraries Government Documents Department
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Anticipated effect of discharging 242-S evaporator cooling water to the ground

Description: The discharge of cooling water, in the amount of 1 to 1.2 billion gallons per year for a period of three years, from the 242-S Evaporator- Crystallizer to the groundwater system will have a measurable effect on the altitude of the water table beneath and directly adjacent to the 200 West Area of the Hanford Reservation. The probability is high that the water levels in well 299-W23-4 and well 699-35-75 adjacent to the 216-U-10 pond will rise from their present altitude of 478 feet to a minimum a… more
Date: September 17, 1971
Creator: Veatch, M.D.
Partner: UNT Libraries Government Documents Department
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Electrolytic dissolver for plutonium metal

Description: Laboratory tests have demonstrated that plutonium metal, as well as aluminum, stainless steel, Hastelloy C, and other alloys, can be electrolytically dissolved in nitric acid using the ''solution contact'' approach. Two sources of plutonium metal were evaluated, weapons' grade and a special reactor grade (42% /sup 240/Pu, 12% /sup 241/Pu) from Savannah River, both yielding a dissolution rate of approximately one gram per ampere-hour. A current flow of 150 amperes was attained at 12 volts (limit… more
Date: September 20, 1971
Creator: Fox, R. D.
Partner: UNT Libraries Government Documents Department
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