PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING AUGUST 1958
Measurements of thermal conductivity and electrical resistivity were continued on irradiated specimens of UO/sub 2/-clad in Zircaloy-2 with NaK as the heat-transfer medium. The creep strength of 0.15% cold-worked Zircaloy-2 is being determined at elevated temperatures. Work continued on the development of highstrength corrosion-resistant Zr alloys. Research to develop a method of sink- float density measarements to identify factors affecting irradiation-induced volume changes in graphite was continued. Single crystals of high-purity Mo are being prepared for irradiation damage studies. Casting methods are presented for Al--U alloys. Time-temperature relationships are being studied during the solidification of small cylindrical U castings to improve the quality of fabricated U fuel slugs. Methods for preparing a thin protective coating of Mo on Croloy are being investigated. Research indicates that in a binary system of UO/sub 2/-- La/sub 2/O/sub 3/ 60 wt.% La/sub 2/O/sub 3/ is required to form a stoichiometric structure after oxidation. Investigations of the hydrides of U- Zr alloy for possible use in gas-cooled reactors were continued. An irradiation- damage program on type 347 stainless steel was undertaken to study the changes in physical properties that are caused by continued exposure to a fast-neutron flux up to 3 x 10/sup 15/ nvt and integrated flux levels of 14 to 16 x 10/sup 22/ nvt. Studies on the properties of Nb--U alloys and the effect of impurities on these properties are presented. Studies on developing Th-U alloys with improved irradiation stability and corrosion resistance are reported. Fabrication techniques for producing dispersion fuel elements with cores of 60 to 90 vol.% UCl. UN. or UC dispersed in stainless steel. Mo. Nb. and Cr are being investigated. Gas-pressure bonding of Mo- and Nb-clad fuel elements is presented. Work was continued on fatigue studies of Inconel. No severe attack of Ti specimens was observed in any of the studies involving Darex Process solutions. Stress-relief treatments were not effective in improving the corrosion resistance of Carpenter 20 Cb to Sulfex-- Thorex solutions. Studies of the fluoride- volatility process have shown fairly high corrosion rates. Casting techniques. irradiationcapsule design, and fission-product release from irradiated UC are presented. The postirradiation examination of fuel element OMRE-3 is approaching completion. Creep data are presented on thermally degassed finegrained sintered Ta sheet tested at 1200 deg F in a He atmosphere. Mixing studies of a model of the PWR core have been resumed. Some improvements were found from the use of deflector vanes over each inlet. In the Maritime Gas Cooled Reactor program a study is under way to investigate the effects of radiation on the reactions of stainless steel cladding with CCl and graphite. The Nuclesr Merchant Ship Reactor development prograin is concerned with testing prototype UO/sub 2/ fuel pins under anticipated NMSR reactor conditions in the MTR. (For preceding period see BMI-1280.) (W.L.H.)
- Research Organization:
- Battelle Memorial Inst., Columbus, OH (United States)
- DOE Contract Number:
- W-7405-ENG-92
- NSA Number:
- NSA-13-000749
- OSTI ID:
- 4331867
- Report Number(s):
- BMI-1286
- Resource Relation:
- Other Information: Decl. Oct. 15, 1958. Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ALUMINUM ALLOYS- CASTING- URANIUM ALLOYS
ALUMINUM ALLOYS- CHROMIUM ALLOYS- FATIGUE- INCONEL ALLOYS- MEASURED VALUES- NICKEL ALLOYS- NIOBIUM ALLOYS- TITANIUM ALLOYS
BONDING- FUEL CANS- FUEL ELEMENTS- GASES- MOLYBDENUM- NIOBIUM- PRESSURE
CARBON DIOXIDE- FUEL CANS- GAS COOLANT- GRAPHITE- GRAPHITE MODERATOR- MGCR- RADIATION EFFECTS- STAINLESS STEELS
CARPENTER- CORROSION- HEAT TREATMENTS- NIOBIUM ALLOYS- STAINLESS STEELS- STRESSES- SULFEX PROCESS- THOREX PROCESS- WASTE SOLUTIONS
CASTING- FISSION PRODUCTS- FUEL CANS- IRRADIATION- URANIUM CARBIDES
CASTING- RODS- SOLIDIFICATION- TEMPERATURE- URANIUM
CHEMIC