PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING AUGUST, 1962

Technical Report · Sat Sep 01 04:00:00 EDT 1962

OSTI ID:4751088

Dayton, R W; Dickerson, R F

In Na environment friction and wear tests, self-welding experiments between stainless steel specimens were conducted at 800 deg F without Na. Breakaway friction coeificients were found to be 2.3 and 0.9 and kinetic friction coefficients after breakaway were 1.25 and 0.9. Other programs in progress include irradiation of 347 stainless steel and burnup of boron compounds. In fuels research, thermal-conductivity measurements of (ThgU)C/sub 2/, (ThgU)C and (ThgU)B/sub 4/ were completed. Data on these compounds are tabulated. Data are also given on the physical properties of iron-base Pu alloys for spike fuel applications. In a program to establish understanding of fission-product release in refractory fuels, data were obtained on several fission gases released from UO/ sub 2/ during irradiation. Other continuing programs are reported on radiation stability of UC, high burnup in homogeneous ceramic reactor fuels, and bonding of ceramic fuel elements. A program to determine the feasibility of using in- process isotope neutron sources to produce short-lived tracers for stream analysis is described. Data on neutron activation applications are included. Data obtained in graft polymerization studies of polymethylmethacrylate and vinyl pyrrolidine are given. In research on radioinduced enhanced catalytic activity, catalysts containing up to 65 mc/g of fissionproduct beta activity were used in the dehydration of cyclohexanol. Continued work on evaluation of stresses on sealed radiation sources is reported. Data are included on creep-rupture of cold worked Zircaloy-2 at oxide coatings for fuel particles. Data and information on coating of fuel particles with pyrolytic carbon are given along with data on fission-gas release from coatedparticle fuels and data obtained in post irridiation studies of these fuels. Progress is also reported in radiation damage in ceramics, fission gas diffusion, fuel compatibility, coolant- compatability, fuel particle thermal conductivity, and strain in ceramics caused by fission fragments. Corrosion studies on candidate materials for fluoride- volatility processes are reported. Data are included on creep-rupture of SAP alloys at 700, 800, and 900 deg F. Research on fission product deposition, radiation effects, fabrication of UO/sub 2/--ZrO/sbu 2/ systems, properties of irradiated Hastelloy X, properties of Nb alloys, and on methods of joining metal diaphragms is given. (J.R.D.)

• Research Organization: Battelle Memorial Inst., Columbus, Ohio
• DOE Contract Number: W-7405-ENG-92; W-7405-ENG-92
• NSA Number: NSA-17-006511
• OSTI ID: 4751088
• Report Number(s): BMI-1593(Del.)
• Country of Publication: United States
• Language: English

Related Subjects

ACTIVATION
ALCOHOLS
ALUMINUM
ALUMINUM ALLOYS
BETA PARTICLES
BONDING
BORON COMPOUNDS
BUILDING MATERIALS
BURNUP
CARBON
CATALYSIS
CERAMICS
CHEMICAL REACTIONS
COATING
COLD WORKING
COOLANTS
CORROSION
CREEP
CYCLOALKANES
DEFORMATION
DIFFUSION
ENVIRONMENT
FABRICATION
FAILURES
FISSION PRODUCTS
FLUORIDES
FRICTION
FUEL ELEMENTS
FUELS
GASES
HETEROCYCLICS
HEXANE
HIGH TEMPERATURE
HYDROGEN
IRON ALLOYS
IRRADIATION
ISOTOPES
MATERIALS TESTING
MEASURED VALUES
MECHANICAL PROPERTIES
METALS
METALS, CERAMICS, AND OTHER MATERIALS
METHACRYLIC ACID
METHYL RADICALS
NEUTRON SOURCES
ORGANIC NITROGEN COMPOUNDS
OXIDES
PARTICLES
PLUTONIUM ALLOYS
PO
POLYMERIZATION