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905 Matching Results
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Accidental Radiogold (198Au) Liver Scan Overdose With Fatal Outcome
This report addresses the use of radioisotopes for scanning, which has added significantly to the clinician's ability to detect and interpret disease manifestations.
Date:
October 31, 1969
Creator:
Baron, J.M.; Yachnin, S.; Polcyn, R.; Fitch, F.W. & Sturner, W.G.
Object Type:
Report
System:
The UNT Digital Library
Sol-Gel Processes for Isotopic Heat Sources.
None
Date:
October 31, 1969
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Sodium Chemistry, Fission Product Contamination.
None
Date:
October 31, 1969
Creator:
Silberberg, M.; Guon, J. & Zwetzig, G.
Object Type:
Report
System:
The UNT Digital Library
Discovery and History of $sup 252$Cf.
None
Date:
October 31, 1969
Creator:
Fields, P. R.
Object Type:
Report
System:
The UNT Digital Library
Study of the Effective Two-Body Force Using the $Sup 54$Fe($Sup 3$He,T) Charge Exchange Reaction.
None
Date:
October 31, 1969
Creator:
Hayakawa, S. I.; Kraushaar, J. J.; Kunz, P. D. & Rost, E.
Object Type:
Report
System:
The UNT Digital Library
RADIOCHEMICAL ANALYSES OF $sup 238$PuO$sub 2$ COLLECTED ON IMPACTORS M-15, M-37, M-22, AND M-32.
None
Date:
October 31, 1969
Creator:
Holland, W.D.
Object Type:
Report
System:
The UNT Digital Library
RECOVERY OF PALLADIUM FROM NUCLEAR WASTE SOLUTIONS USING A PACKED COLUMN OF TRICAPRYL MONOMETHYL AMMONIUM CHLORIDE ON AN INERT SUPPORT.
None
Date:
October 31, 1969
Creator:
Colvin, C.A.
Object Type:
Report
System:
The UNT Digital Library
Pacific Northwest Laboratory Monthly Activities Report for January 1967.
None
Date:
October 31, 1969
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
PHYSICO-CHEMICAL STUDIES OF CLAD UO$sub 2$ IN POTENTIAL MELTDOWN ENVIRONMENTS.
Behavior of zirconium alloy clad UO{sub 2} fuel elements in steam and air at 100 deg C to the melting point of UO{sub 2} was studied. Heating tests of Zircaloy-4 tubes with internal pressure show that steam oxidation of the metal results in lower deformation rates, less deformation, and higher failure temperature. Air oxidation of Zircaloy-4 is erratic and occurs at a greater rate than in steam due to the reaction with N in the air. Rate-controlling mechanism for UO{sub 2} oxidation by steam is the diffusion of O through UO{sub 2+x} lattice. The air oxidation rate of 304 stainless steel is about 10{sup 3} times less than the rate in steam up to 1370 deg C due to excess CR{sub 2}O{sub 3} film formation. During steam oxidation, the film provides less protection because of its spinel structure. Tensile strength of annealed 304 L decreased from 0.66 kg/mm{sup 2} at room temperature to 0.86 kg/mm{sup 2} at 1375 deg C. Thermal conductivity increased with temperature. The spectral emittance of Zircaloy-4 varied. Solution of O in the metal during prolonged heating caused spectral and total emittance to approach the values of the unoxidized metal. (F.S.)
Date:
October 31, 1969
Creator:
White, J.F.
Object Type:
Report
System:
The UNT Digital Library
Search for Neutrinos From the Sun.
None
Date:
October 31, 1969
Creator:
Davis, R., Jr.
Object Type:
Report
System:
The UNT Digital Library
THIRD GENERATION COMPUTER USED TO CONTROL FUEL ELEMENT ASSEMBLY.
None
Date:
October 31, 1969
Creator:
Cort, G.E. & Agosti, R.J.
Object Type:
Report
System:
The UNT Digital Library
AEC Unclassified Programs. Annual Technical Progress Report, Fiscal Year 1968.
This report addresses the AEC Unclassified Programs which includes the evaluation, production, and maintenance of an up-to-date set of basic nuclear data.
Date:
October 31, 1969
Creator:
United States. Department of Energy.
Object Type:
Report
System:
The UNT Digital Library
Animal Metabolic Studies of Strontium and Calcium With Specific Reference to Fallout Radionuclides. Second Comprehensive Report, August 16, 1966--August 15, 1969.
This report summarizes the animal metabolic studies of strontium and calcium with specific reference to fallout radionuclides
Date:
October 31, 1969
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
FAST BREEDER REACTOR THERMOCOUPLE DEVELOPMENT.
Studies of very high-temperature thermocouple characteristics for instrumentation and electrical components used in fast breeder reactors showed that the thermoelectric emf produced along BeO, HfO{sub 2}, or ThO{sub 2} insulators can affect the output of the thermoelements. Bare-wire thermocouples are influenced by environment. Radiation effects on W versus W - Re thermocouples in the ORR after ~ 2 months in a 1.2 x 10{sup 14}n/cm{sup 2}-sec thermal and 2.1 x 10{sup 13}n/cm{sup 2}-sec fast flux indicate that W and W - Re thermoelements shift similarly in thermal emf, resulting in a positive error of 5 deg C. Hafnates such as CaHfO{sub 3}, SrHfO{sub 3}, and SrZrO{sub 3} were found to be inferior to BeO and HfO{sub 2} as thermocouple insulating materials. (F.S.)
Date:
October 31, 1969
Creator:
Funston, E.S. & Kuhlman, W.C.
Object Type:
Report
System:
The UNT Digital Library
Doppler and Related Measurements in a Soft Fast-Reactor Spectrum.
This report deals with a group of both theoretical and experimental investigations which have been carried out, utilizing Core 15, one in a series of critical assemblies that have been constructed at Atomics International's Epithermal Critical Experiments Laboratory (ECEL).
Date:
October 31, 1969
Creator:
Springer, T. H.; Tuttle, R. J.; Otter, J. M. & Paschall, R. K.
Object Type:
Report
System:
The UNT Digital Library
PHYSICO-CHEMICAL STUDIES OF Fe--Cr--Al-CLAD FUEL SYSTEMS.
Reactions which can occur between oxidation-resistant Fe - CR - AL base alloys and UO{sub 2} at 500 to 1200 deg C are discussed. Aluminum in the Fe - Cr - Al-base cladding reduces the UO{sub 2} in the cermet fuels at 1000 to 1200 deg C. The U dissolves and diffuses through the cladding and is converted to an oxide. Oxygen combines with Al forming Al{sub 2}O{sub 3} which inhibits Al diffusion into the UO{sub 2}. The diffusion for Al in Cr leads to the development of a Cr barrier and reduces the Al - UO{sub 2} interaction and eliminates surface contamination. Free U as substoichiometric UO{sub 2-x} diffuses through 0.38 mm cladding within 100 hrs at 1000 deg C or in 6 hrs at 1200 deg C. At 1000 deg C, U solubility in Fe - Cr - Al-base alloy is 0.1 to 0.2% and its diffusion coefficient is in the range of 10{sup -9} to 10{sup -10} cm{sup 2}/cm. (F.S.)
Date:
October 31, 1969
Creator:
Edwards, H.S. & Bohlander, K.M.
Object Type:
Report
System:
The UNT Digital Library
Advanced Heat Pipe Thermionic Technology. Topical Report for Task Ii. Development of Adsorption Reservoir. Period Covered: May 1, 1968--February 28, 1969.
This report covers work performed on the development of an integral adsorption reservoir thermionic converter.
Date:
October 31, 1969
Creator:
Freggens, R.A.
Object Type:
Report
System:
The UNT Digital Library
EQUIPMENT AND TECHNIQUES FOR MEASUREMENTS OF THERMAL CONDUCTIVITY, THERMAL EXPANSION, AND ASSOCIATED PROPERTIES ABOVE 1000$sup 0$C.
None
Date:
October 31, 1969
Creator:
Wagner, P.
Object Type:
Report
System:
The UNT Digital Library
RECOIL STUDIES IN CHEMICAL DYNAMICS. Progress Report, January 1, 1968-- December 31, 1968.
None
Date:
October 31, 1969
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
THE OAK RIDGE GASEOUS DIFFUSION PLANT FUEL REPROCESSING PROGRAM.
None
Date:
October 31, 1969
Creator:
Merriman, J.R. & Pashley, J.H.
Object Type:
Report
System:
The UNT Digital Library
Control Characteristics of Rankine Cycle Systems Which Simulate the Mpre Fluid System.
In conjunction with the Medium power Reactor Experiment Program at ORNL, studies were conducted on two single-loop Rankine cycle systems. These systems were controlled using the same design concept which has been proposed for control of the MPRE fluid system. Experiments were run with water and potassium test facilities which were reduced scale electrically heated mockups of the proposed reactor and power recovery system. Results from these studies demonstrate that with proper design, the distribution of liquid inventory within the system can be controlled by the degree of cavitation occurring in the turbine-driven centrifugal boiler feed pump. Boiler power changes were made over a wide range and no operator action was required. The changes in fluid flow requirements were accommodated by a variation in the degree of pump cavitation occurring. Step changes in power were imposed on the boiler and there was no indication of instabilities in the fluid system.
Date:
October 31, 1969
Creator:
Yarosh, M.M.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Engineering Department Annual Report, December 31, 1968.
None
Date:
October 31, 1969
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Advanced Heat Pipe Thermionic Technology. Task I. Development of High Voltage Module. Mid-Term Status Report, May 1, 1968--February 28, 1969.
This report addresses he design of a heat pipe-thermionic module concept capable of output potentials as high as 28 volts.
Date:
October 31, 1969
Creator:
Longsderff, R.W.
Object Type:
Report
System:
The UNT Digital Library
Zircaloy-Clad UO2 Fuel Rod Evaluation Program. Quarterly Progress Report Nos. 6 and 7, February--July 1969
None
Date:
December 31, 1969
Creator:
Megerth, F. H.
Object Type:
Report
System:
The UNT Digital Library