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Title: PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JANUARY, 1959

Abstract

Thermal-conductivity measurements are in progress on an unirradiated, unclad, natural U specimen. Data are presented on thermal conductivity measurements performed on UO/sub 2/. The creep properties of annealed and of 15% cold-worked Zircaloy-2 are being studied. A program was initiated to evaluate loss-of-coolant incidents in the PRTR by means of simulation on a digital computer. Research on the casting of hollow Al-35 wt. extrusion billets is reported. Further refinement of the method developed for the analysis of Mg in cement is in progress. The infrared and gaschromatography analysis of irradiated dodecane, decane, cetane. and octane, and their urea complexes, were continued. The manner in which U metal solidifies in cylindrical graphite molds is under study. Work has continued on development of a stabilized hightemperature nuclear fuel capable of operation in either oxidizing or reducing atmospheres. Progress in the stud of potential fueled moderators has continued with the determination of hydrogen-absorption isotherms for the Zr-25 wt. alloy. The effect of fast-neutron flux on the mechanical properties of AISI Tvpe 347 stainless steel are being determined and evaluated. The forging of Nb-U alloys is reported. Thorium-uranium alloys are being studied for the purpose of developing improved corrosion resistance and irradiation stability ofmore » the alloy by means of alloying and control of processing variables. The causes of fission-gas loss from refractory fuel materials is being investigated. Cermet fuel materials consisting of from 60 to 90 vol. % U0/sub 2/, UN, or UC dispersed in a stainless steel or Nb matrix are being investigated. The gas-pressure bonding technique is being investigated for cladding and bonding Nband Mo-base fuel elements and assemblies. Dispersion fuels consisting of UC and UN dispersed in stainless steel were irradiated in the WTR. Stress-cycling tests were continued on Inconel specimens at 1300 and 1500 F, cycled at 1 cps. The investigation of temperature and frequency dependence of fatigue properties of INOR-8 alloy is being investigated, Studies of U compounds and the mechanism of thermal migration of hydrogen in zirconium are in progress. In the research on thermal migration of H/sub 2/ in Zr, new data on the diffusion coefficients of H/sub 2/ in beta Zr were obtained. Data are presented on postirradiation examination of three pairs of fueled-graphite spheres. The evaluation of materials of construction for use in the Darex, SulfexThorex, Zirflex. and Fluoride-Volatility processes of nuclear fuel recovery was continued. Uranium carbide containing 5 wt. % carbon is being studied as a fuel for the SRE. A study of the properties of Ta-W alloys is continuing. A compartmentalized flat-plate Zircaloy2-clad fuel element containing UO/sub 2/ cores is being considered for PWR Core-2. Techniques for the fabrication of graphite-matrix fuel cores containing 20 vol. % UC in form of UC and UC/sub 2/ are reported. (For preceding period see BMI-1307.) (W.L.H.)« less

Authors:
;
Publication Date:
Research Org.:
Battelle Memorial Inst., Columbus, Ohio
OSTI Identifier:
4245308
Report Number(s):
BMI-1315
NSA Number:
NSA-13-016197
DOE Contract Number:  
W-7405-ENG-92
Resource Type:
Technical Report
Resource Relation:
Other Information: Decl. June 12, 1959. Orig. Receipt Date: 31-DEC-59
Country of Publication:
United States
Language:
English
Subject:
METALLURGY AND CERAMICS; ADSORPTION; ALKANES; ALLOTROPY; ALUMINUM ALLOYS; ANNEALING; BONDING; BUILDING MATERIALS; CASTING; CEMENTS; CERMETS; CETANE; CHROMATOGRAPHY; CHROMIUM ALLOYS; COLD WORKING; COMPUTERS; CONTROL; COOLANTS; CORROSION; CREEP; CYLINDERS; DAREX PROCESS; DODECANE; EXTRUSION; FABRICATION; FAST NEUTRONS; FATIGUE; FISSION PRODUCTS; FLUORIDES; FORGING; FREQUENCY; FUEL ELEMENTS; FUELS; GASES; GRAPHITE; HIGH TEMPERATURE; HYDROGEN; INCONEL ALLOYS; INFRARED RADIATION; INOR-8; IRRADIATION; LEAKS; MAGNESIUM; MATERIALS TESTING; MEASURED VALUES; MECHANICAL PROPERTIES; MODERATORS; MOLYBDENUM ALLOYS; NEUTRON FLUX; NICKEL ALLOYS; NIOBIUM; NIOBIUM ALLOYS; OCTANE; OXID

Citation Formats

Dayton, R.W., and Tipton, C.R. Jr. PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JANUARY, 1959. United States: N. p., 1959. Web. doi:10.2172/4245308.
Dayton, R.W., & Tipton, C.R. Jr. PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JANUARY, 1959. United States. doi:10.2172/4245308.
Dayton, R.W., and Tipton, C.R. Jr. Sun . "PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JANUARY, 1959". United States. doi:10.2172/4245308. https://www.osti.gov/servlets/purl/4245308.
@article{osti_4245308,
title = {PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JANUARY, 1959},
author = {Dayton, R.W. and Tipton, C.R. Jr.},
abstractNote = {Thermal-conductivity measurements are in progress on an unirradiated, unclad, natural U specimen. Data are presented on thermal conductivity measurements performed on UO/sub 2/. The creep properties of annealed and of 15% cold-worked Zircaloy-2 are being studied. A program was initiated to evaluate loss-of-coolant incidents in the PRTR by means of simulation on a digital computer. Research on the casting of hollow Al-35 wt. extrusion billets is reported. Further refinement of the method developed for the analysis of Mg in cement is in progress. The infrared and gaschromatography analysis of irradiated dodecane, decane, cetane. and octane, and their urea complexes, were continued. The manner in which U metal solidifies in cylindrical graphite molds is under study. Work has continued on development of a stabilized hightemperature nuclear fuel capable of operation in either oxidizing or reducing atmospheres. Progress in the stud of potential fueled moderators has continued with the determination of hydrogen-absorption isotherms for the Zr-25 wt. alloy. The effect of fast-neutron flux on the mechanical properties of AISI Tvpe 347 stainless steel are being determined and evaluated. The forging of Nb-U alloys is reported. Thorium-uranium alloys are being studied for the purpose of developing improved corrosion resistance and irradiation stability of the alloy by means of alloying and control of processing variables. The causes of fission-gas loss from refractory fuel materials is being investigated. Cermet fuel materials consisting of from 60 to 90 vol. % U0/sub 2/, UN, or UC dispersed in a stainless steel or Nb matrix are being investigated. The gas-pressure bonding technique is being investigated for cladding and bonding Nband Mo-base fuel elements and assemblies. Dispersion fuels consisting of UC and UN dispersed in stainless steel were irradiated in the WTR. Stress-cycling tests were continued on Inconel specimens at 1300 and 1500 F, cycled at 1 cps. The investigation of temperature and frequency dependence of fatigue properties of INOR-8 alloy is being investigated, Studies of U compounds and the mechanism of thermal migration of hydrogen in zirconium are in progress. In the research on thermal migration of H/sub 2/ in Zr, new data on the diffusion coefficients of H/sub 2/ in beta Zr were obtained. Data are presented on postirradiation examination of three pairs of fueled-graphite spheres. The evaluation of materials of construction for use in the Darex, SulfexThorex, Zirflex. and Fluoride-Volatility processes of nuclear fuel recovery was continued. Uranium carbide containing 5 wt. % carbon is being studied as a fuel for the SRE. A study of the properties of Ta-W alloys is continuing. A compartmentalized flat-plate Zircaloy2-clad fuel element containing UO/sub 2/ cores is being considered for PWR Core-2. Techniques for the fabrication of graphite-matrix fuel cores containing 20 vol. % UC in form of UC and UC/sub 2/ are reported. (For preceding period see BMI-1307.) (W.L.H.)},
doi = {10.2172/4245308},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {2}
}