PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MARCH 1961
Preparation of a gamma U/sub 3/O/sub 8/ single crystal for x ray examination is reported. Data from developmental work on binary Nb alloys are presented on stresses to produce deformation rates of 0.001, 0.01, and 0.1% per hr at 650, 800, and 1000 deg C. Developmental work on miniature heating elements for use in a power-balancing thermal-neutron flux sensor is reported for imbedded wire and film-conductance elements. In development of Th-- U alloys, chemical analysis data obtained from skull-cast samples are given. Results of a 1-month test on corrosion of Th-base compounds by NaK at 1200 deg F are tabulated. Data are given on mechanical and structural properties of Pu alloys being developed for high temperature propulsion uses. Continued studies of PuO/sub 2/ compatability with various stainless steels are reported. Efforts were devoted to characterizing sintered UO/sub 2/ bodies by quantitative metallography. Techniques were developed for fabrication of cermet fuels containing 80 vol.% UO/ sub 2/ and the remainder metals such as Cr, Mo, Nb or stainless steel. Fabrication studies on UN and UC fuels were conducted along with studies of gas pressure bonding methods. In development of UC, data on U--C systems at 1000 to 1500 deg C were obtained. Tests to determine the interdiffusion rates for C and U were completed. Irradiation of a capsule containing U--5 wt.% C was completed, and data are included. Experimental runs using the process-model system to study Mn removal from filtrates were completed. In graft polymerization studies, the effect of polymer structure on the efficiency of free-radical site formation was continued. In the joint U. S.-Euratom program, studies concenned obtaining information on void content and heat-transfer relations in forced-convection, two- phase flow, light-water systems. Development of UN as a fuel element is also in progress. Research is being conducted at HAPO on reactor materials in NPR and on operation of PRTR. Creep properties of Zircaloy-2 are being studied and radiation effects on thermal and electric properties of UO/sub 2/ are being examined. In a program to evaluate various coated-particle fuels, fission product retention as a function of burnup and operating temperature is being measured. The program is also aimed at optimization of the most promising coating materials and their reactions in radiation environments and gas coolants. In a study of spent fuel recovery, corrosion of process vessels and equlpment from service in ORNL Fluoride-Volatility Pilot Plant is being evaluated. Evaluation of fueled-graphite spheres from 3 vendors for use in the Pebble Bed Reactor program are reported. Direct joining and transition joining of Zircaloy- 2 to type 410 stainless steel are being investigated. The program also includes end capping Zircaloy-2 fuel sheaths by friction techniques. Radiation studies of SM-2 fuels are reported and fabrication methods for ML-1 fuels are described. Corrosion of Th and U and their alloys is being studied. Included are research and development on application of electroplated coatings. Techniques for Be cladding of UO/sub 2/ fuel elements are being developed; data on two specimens are included. (J.R.D.)
- Research Organization:
- Battelle Memorial Inst., Columbus, OH (United States)
- DOE Contract Number:
- W-7405-ENG-92
- NSA Number:
- NSA-15-019076
- OSTI ID:
- 4007084
- Report Number(s):
- BMI-1509(Del.)
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-61
- Country of Publication:
- United States
- Language:
- English
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ADSORPTION
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BONDING
BURNUP
CANNING
CARBON
CASTING
CERMETS
CHEMICAL REACTIONS
CHROMIUM
CONFIGURATION
CORROSION
CREEP
DEFORMATION
DIFFUSION
EFFICIENCY
ELECTRIC PROPERTIES
ELECTRICITY
ELECTROPLATING
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LABORATORY EQUIPMENT
LATTICES
LIQUID METALS
MANGANESE
MATERIALS TESTING
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MOLYBDENUM
MONOCRYSTALS
NIOBIUM
NIOBIUM ALLOYS
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