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AEC FUELS AND MATERIALS DEVELOPMENT PROGRAM. Seventh Annual Report.

Description: This report is the seventh annual report of the unclassified portion of the Fuels and Materials Development Programs being conducted by the General Electric Company's Nuclear Materials and Propulsion Operation under Contract AT(40-1)-2847, issued by the Fuels and Materials Branch, Division of Reactor Development and Technology, of the Atomic Energy Commission. This report covers the period from January 31, 1967 to January 31, 1968, and thus also serves as the quarterly progress report for the fā€¦ more
Date: January 1, 1968
Partner: UNT Libraries Government Documents Department
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PHYSICO-CHEMICAL STUDIES OF CLAD UO$sub 2$ IN POTENTIAL MELTDOWN ENVIRONMENTS.

Description: Behavior of zirconium alloy clad UO{sub 2} fuel elements in steam and air at 100 deg C to the melting point of UO{sub 2} was studied. Heating tests of Zircaloy-4 tubes with internal pressure show that steam oxidation of the metal results in lower deformation rates, less deformation, and higher failure temperature. Air oxidation of Zircaloy-4 is erratic and occurs at a greater rate than in steam due to the reaction with N in the air. Rate-controlling mechanism for UO{sub 2} oxidation by steam isā€¦ more
Date: October 31, 1969
Creator: White, J.F.
Partner: UNT Libraries Government Documents Department
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FAST BREEDER REACTOR THERMOCOUPLE DEVELOPMENT.

Description: Studies of very high-temperature thermocouple characteristics for instrumentation and electrical components used in fast breeder reactors showed that the thermoelectric emf produced along BeO, HfO{sub 2}, or ThO{sub 2} insulators can affect the output of the thermoelements. Bare-wire thermocouples are influenced by environment. Radiation effects on W versus W - Re thermocouples in the ORR after ~ 2 months in a 1.2 x 10{sup 14}n/cm{sup 2}-sec thermal and 2.1 x 10{sup 13}n/cm{sup 2}-sec fast fluxā€¦ more
Date: October 31, 1969
Creator: Funston, E.S. & Kuhlman, W.C.
Partner: UNT Libraries Government Documents Department
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PHYSICO-CHEMICAL STUDIES OF Fe--Cr--Al-CLAD FUEL SYSTEMS.

Description: Reactions which can occur between oxidation-resistant Fe - CR - AL base alloys and UO{sub 2} at 500 to 1200 deg C are discussed. Aluminum in the Fe - Cr - Al-base cladding reduces the UO{sub 2} in the cermet fuels at 1000 to 1200 deg C. The U dissolves and diffuses through the cladding and is converted to an oxide. Oxygen combines with Al forming Al{sub 2}O{sub 3} which inhibits Al diffusion into the UO{sub 2}. The diffusion for Al in Cr leads to the development of a Cr barrier and reduces the ā€¦ more
Date: October 31, 1969
Creator: Edwards, H.S. & Bohlander, K.M.
Partner: UNT Libraries Government Documents Department
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ADVANCED PRESSURE VESSEL MATERIALS.

Description: Data on 5Cr - 3Mo - 12Ni alloy, PH13 - 8Mo and Iconel 718 for pressure vessel application are given. The 5Cr - 3Mo - 12Ni posseses characteristics suited to uniform aging of heavy sections. Tensile and toughness properties are good, and structural stability up to 315 deg C is adequate. Weldability with 12Ni - 3Cr - 3Mo filler material is good but 12Ni - 5Cr - 3Mo filler is more efficient. Aging characteristics of PH13 - 8Mo may not be suited to uniform aging of heavy sections. Excellent tensileā€¦ more
Date: October 31, 1969
Creator: Robertshaw, F.C.; Stephan, H.R. & McConnelee, J.E.
Partner: UNT Libraries Government Documents Department
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High-Temperature Research on Carbides for Fuel and Structural Applications.

Description: High temperature physico-chemical properties of refractory carbides for fuel and structural use were determined. Density and phases of vacuum hot pressed HfC, TaC, and ZrC are tabulated and the diffusion coefficients, lattice parameters, and thermodynamic properties of TaC and UC are given. (F.S.)
Date: October 31, 1969
Creator: White, J. F. & Juenke, E. F.
Partner: UNT Libraries Government Documents Department
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PHYSICAL AND MECHANICAL PROPERTIES OF REACTOR MATERIALS.

Description: High temperature (to 3000 deg C) physical and mechanical properties for commercially available and newly developed materials being considered for use in high temperature reactors were measured. Creep, stress rupture, ductility, microstructure, and failure mechanism for tungsten were determined. Values were found for creep of as cast Mo; creep rupture of Re, Mo - Re - W, Mo - W, and Re - W; thermal conductivity and electrical resistivity of Re - W; and enthalpies, heat content and heat capacity ā€¦ more
Date: October 31, 1969
Creator: Conway, J.B. & Flagella, P.N.
Partner: UNT Libraries Government Documents Department
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PHYSICAL METALLURGY OF FAST BREEDER REACTOR CLADDING MATERIALS AND REFRACTORY METALS.

Description: Studies on Re - Mo - W alloys led to lower cost production procedures and greatly improved room temperature ductility properties of powder metallurgy materials used for fast breeder reactor fuel cladding materials. Data are presented for ductility, grain size, hardness, recrystallization, and changes in aging at temperatures up to 2000 deg C for periods up to 1000 hrs. (F.S.)
Date: October 31, 1969
Creator: Collins, C.G. & Bohlander, K.M.
Partner: UNT Libraries Government Documents Department
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Brayton Cycle Study

Description: The purpose of the study was to provide a comparison of the characteristics of a space power system operating on the Brayton cycle with either neon or argon.
Date: January 1, 1964
Creator: Semple, E.L. & Simpson, J.D.
Partner: UNT Libraries Government Documents Department
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