PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MAY 1958
Thermal-conductivity measuremerts of unirradiated U0/sub 2/ were started. The creep and rupture strengths of 15% cold-worked Zircaloy-2 were determined at 290, 345, and 400 C. Corrosion testing of high-strength zirconium alloys with Nb and Mo additives at 300 C is in progress. Centrifugal-casting studies of air-melted Al-25 wt.% U extrusion billets are described. Optimum time- temperature-pressure relationships were determined for hydrostatic pressure bonding of nickel-plated uranium slugs in aluminum sheaths. Development of a high-uranium fuel alloy that has improved corrosion resistance in 300 C water was undertaken. Studies concerned with radiation stability of U-Zr alloys, the development of gamma-phase U alloys, and the mechanism of aqueous corrosion are preseuted. Fatigue studies of Inconel and INOR-8 are in progress. A study is presented of the oxidation behavior of unalloyed Nb and Nb alloys with the objective of correlating the oxidation hehavior of the metal with the effects of alloying on a fundamental basis. An investigation of the effects of cation valence of solute additions upon the stability of U0/sup 2/ is in progress. Dry- friction and sodium-lubricated tests were completed using a Mo-Mo rubbing combination. An investigation is in progress with the purpose of analyzing the pressure-bonding process from the standpoint of the creep properties of the material involved. A study of the kinetics and mechanisms of the reaction of H/ sub 2/ with Nb was made. Experimeutal and theoretical study of the mechanism of H/sub 2/ migration in zirconium hydride has cortinued. Titanium coutinues to have merit for use as a material of construction of the Darex dissolver and feed- adjustment tank. The evaluation of various metals for use as container materials for the dissolution step of a proposed Sulfex-Thorex process has coutinued. Materials for the construction of the hydrofluorinator in the fluoride volatility process are being tested. Investigations of the creep behavior of Ta in Na in an inert atmosphere (He) and a study of factors concerned with the welding of Ta are preserted. Stsdies of mixing in a flow model of the PWR were coutinued. Pressure bonding of Zircaloy-2-clad fuel elements containing compartmented oxide fuel plates are being evaluated for use in PWR Core 2. The evaluation of UC as a reactor fuel is continuing. Evaluation of various fanel materials for the Nuclear Merchant Ship Reactor is presented. (For preceding period see BMl-1262.) (W.L.H.)
- Research Organization:
- Battelle Memorial Inst., Columbus, OH (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-7405-ENG-92
- NSA Number:
- NSA-13-002176
- OSTI ID:
- 4280000
- Report Number(s):
- BMI-1267
- Resource Relation:
- Other Information: Decl. June 18, 1958. Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
AIR- ALUMINUM ALLOYS- CASTING- MELTING- URANIUM ALLOYS
ALLOTROPY- CORROSION- RADIATION EFFECTS- STABILITY- URANIUM ALLOYS- WATER- ZIRCONIUM ALLOYS
ALUMINUM ALLOYS- CHROMIUM ALLOYS- FATIGUE- INCONEL ALLOYS- INOR-8- MOLYBDENUM ALLOYS- NICKEL ALLOYS- NIOBIUM ALLOYS- TENSILE PROPERTIES- TITANIUM ALLOYS
ALUMINUM- BONDING- CANNING- NICKEL- PLATING- PRESSURE- RODS- TEMPERATURE- URANIUM
BEHAVIOR- CREEP- HELIUM- SODIUM- TANTALUM- WELDING
BEHAVIOR- NIOBIUM- NIOBIUM ALLOYS- OXIDATION
BONDING- CREEP- MATERIALS TESTING- PRESSURE
BONDING- FUEL CANS- FUEL ELEMENTS- OXIDES- PLATES- PRESSURE- PWR- REACTORS-