PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MAY 1960
The investigation of the stabilizing influence of oside additions to UO/ sub 2/ was continued. The effects of fast-neutron irradiation upon the mechanical properties of Type 347 stainless steel are being investigated. Tensile data are reported for alloys of Nb-Cr and Nb-Zr. The major effect of fast-neutron irradiation on the creep properties of Zircaloy-2 is being studied by comparing the in-reactor creep behavior of the alloy with out-of-reactor creep properties. New methods for the determination of low concentrations of oxygen in sodium are being investigated. The mechanisms of wear and friction of various metals in sliding contact in liquid sodium are being studied. Data are presented on corrosion properties, short-time tensile properties, stress-rupture properties, and electrical resistivity for Nb--U alloys. The development of Th and Th--U alloys with improved radiation resistance is being investigated. A program is reported for the determination of diffusion coefficients of Xe in single-crystal UO/sub 2/ specimens and the in-pile study of fission-product release from sintered UO/sub 2/. Thermal-conductivity, thermal-expansion, electrical-resistivity, and modulus-of-rupture measurements are being made on 80 vol.% UO/sub 2/ cermets. Techniques for the fabrication of compartmented Mo- and Nbclad UO/sub 2/ and cermet fuels are being investigated. Compaction studies of UO/sub 2/ were undertaken to provide core materials which will achieve a range of desired densities on pressure bonding. The fabrication of Type 304 stainiess steel-clad UO/sub 2/ rod, tube, and flat-plate elements and flat-plate assemblies was accomplished by gas pressure bonding. Various methods for economically producing dense UC components by powder-metallurgical techniques are being investigated. A study of the properties of UC is under way. Thermal-gradient experiments are being performed to establish a theoretical basis for the prediction of hydrogen migration in zirconium hydride. Experiments were continued in producing single crystals of UO/sub 2/. Portland cement samples were analyzed for sulfate content using a radiometric method involving the precipitation of Sr/sup 89/SO/sub 4/. Solution-annealed strips of welding alloys for use with Hastelloy F to contain decladding solutions were prepared for welding and corrosion evaluations. A study is being made of the effects of irradiation on cladding- amd core-dissolution processes. Uranium carbide shot was coated with 160 ation of carbon by the thermal decomposition of acetylene in a fluidized bed of the shot. Two programs concerned with investigations of Ta and Ta-base materials of interest for containment of molten Pu-alloy fuels are under way. Fission-gas release from BeO--UO/sub 2/ is being investigated by heat treating neutron-activated sintered pellets. A study of the radiation stability of ceramic-type fuels under conditions simulating those of the MGCR design is in progress. Purther experimental and theoretical studies were carried out to determine the feasibility of coating and preparing U and Th carbides by vapor deposition reactions in a fluidized bed. Methods are being developed for preparing instrumented fuel plates for use in 8M-1 type fuel elements for in-pile test evaluation. Materials were selected and techniques were established for the fabrication of SM-2 reference fuel elements. For the ML- I Reactor Hastelloy X will be used as the fuel-element cladding material. (For preceding penicd see BMI-1434.) (W.L.H.)
- Research Organization:
- Battelle Memorial Inst., Columbus, OH (United States)
- NSA Number:
- NSA-14-019311
- OSTI ID:
- 4177197
- Report Number(s):
- BMI-1442(Rev.)
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
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ACETYLENES- CARBIDES- CARBON- COATING- DECOMPOSITION- FLUIDIZATION- HIGH TEMPERATURE- URANIUM COMPOUNDS
ACTIVATION- BERYLLIUM OXIDES- FISSION PRODUCTS- GASES- HEAT TREATMENTS- NEUTRONS- PELLETS- SINTERING- URANIUM DIOXIDE- WASTE DISPOSAL
ALLOYS- CHROMIUM ALLOYS- COBALT ALLOYS- CORROSION- FUEL CANS- NICKEL ALLOYS- SOLUTIONS- VESSELS- WELDING
BONDING- CERMETS- COMPACTS- DENSITY- FABRICATION- FUEL CANS- FUELS- GASES- MOLYBDENUM- NIOBIUM- PLATES- - PRESSURE- RODS- STAINLESS STEELS- TUBES- URANIUM DIOXIDE
CARBIDES- COATING- FLUIDIZATION- PREPARATION- THORIUM CARBIDES- URANIUM COMPOUNDS- VAPORS
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