PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MAY 1959
Data are presented on the electrical conductivity of unirradiated UO/sub 2/. A stud of the creep properties of annealed and of 15% cold-worked Zircaloy-2 at 290, 345, and 400 deg C is in progress. High-purity Mo single crystals are being grown in a modified Andrade furnace. Research to develop a method of sink- float density measurement to identify factors affecting irradiation-induced volume changes in graphite was continued. The simulation of conditions after a lossof-coolant incident in the PRTR by means of a digital computer was continued. Tensile data are given on Al--as wt. % U alloys with 3 wt. % ternary additions of Si, Sn, and Zr. Work was continued on the free-radical and peroxy grafting of polymethylmethacrylate and polyacetylmethacrylate. The manner in which uranium solidifies in cylindrical graphite molds is being studied. An investigation is being made of the effect of oxide additions (CaO and La/sub 2/O/sub 3/) to UO/sub 2/ in preventing the transformation and volatility associated with the formation of U/sub 3/O/sub 8/ during oxidation. Postirradiation studies are in progress on the specimens of hydrided Zr--2 wt. % U which were irradiated in the MTR. An irradiation-surveillance program is being conducted on AISI Type 347 stainless steel. An evaluation of several Nb-base alloys for possible application as alternate cladding material in future EBR cores is being made. Corrosion data are presented for commercial purity Nb-Zr, Nb-W, Nb-Mo, Nb-V, Nb-Fe, Nb-Ti, Nb-Ti- Cr-, Nb-Ti-Mo, and Nb-Ti-V alloys in 750 deg F steam and 650 deg F water. Corrosion data are reported for Nb-U alloys in air and in water after 14 and 25 days exposure. Thermal analysis data are presented for Th--U--Zr and Th--U--Zr-- Nb alloys. Specimens of single-crystal UO/sub 2/ are being prepared for study of fission-gas diffusion coefficients by low temperature irradiation and subsequent heating to collect the fission gases. The gas-pressure bonding technique is being studied as a possible method for cladding ceramic and cermet fuels with Mo and Nb. The high-temperature irradiation behavior of dispersion fuel elements consisting of 24 wt. % UN or UC dispersed in stainless steel and clad with stainless steel is being evaluated. The solid-state bonding of metals by application of heat and pressure is being studied in an attempt to establish the mechanism and kinetics of the process. Data are presented on the green compacting of U% powders under various conditions. Several methods of fabricating UC of high density are being studied. Data are presented on the effects of impurities on some properties of cast UC. A program to obtain basic fatigue information on Inconel is presented. A program concerned with the investigation of the temperature and frequency dependence of fatigue properties of INOR-8 alloy is reported Preliminary experiments were conducted with the apparatus designed for the study-of the migration of hydrogen in Zr under the influence of a thermal gradient. Fueled-graphite spheres are being evaluated with respect to selected thermal and mechanical properties. Irradiation data are presented on UC specimens. A Zircaloy-2-clad Compartmented flat-plate fuel element containg UO/sub 2/ cores is being considered for the PWR. Core-2. Techniques are being investigated for use in the fabrication of fuel elements containing cores of 26 wt. % UO/sub 2/-1.1 wt. % ZrB/sub 2/ dispersed in a prealloyed Type 347 stainless steel matrix. (For preceding period see BMI-1340.) (W.L.H.)
- Research Organization:
- Battelle Memorial Inst., Columbus, OH (United States)
- DOE Contract Number:
- W-7405-ENG-92
- NSA Number:
- NSA-13-021169
- OSTI ID:
- 4220558
- Report Number(s):
- BMI-1346
- Resource Relation:
- Other Information: Decl. July 17, 1959. Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ACCIDENTS- COMPUTERS- COOLANTS- DIGITAL SYSTEMS- LEAKS- PRTR- REACTORS
ACETYL RADICALS- FREE RADICALS- METHACRYLATES- METHACRYLIC ACID- METHYL RADICALS- POLYMERS
ALUMINUM ALLOYS- MEASURED VALUES- SILICIDES- TENSILE PROPERTIES- TIN ALLOYS- URANIUM ALLOYS- ZIRCONIUM ALLOYS
ANNEALING- COLD WORKING- CREEP- MEASURED VALUES- TEMPERATURE- TENSILE PROPERTIES- ZIRCALOY
BONDING- CANNING- CERAMICS- CERMETS- FUELS- GASES- MOLYBDENUM- NIOBIUM- PRESSURE
BONDING- HEATING- METALS- PRESSURE
CALCIUM OXIDES- CHEMICAL REACTIONS- LANTHANUM OXIDES- OXIDATION- URANIUM DIOXIDE- U3O8- VOLATILITY
CASTING- CYLINDERS- GRA