Collection
Serial/Series Title
AEC research and development report
2
Atomic Energy Commission Reports
2
Army Gas-Cooled Reactor Systems Program Progress Report
1
ETL (Series) (United States. Army. Corps of Engineers)
1
GA (Series) (San Diego, Calif.)
1
General Dynamics Corporation Reports
1
IDO
1
TID
1
U.S. Atomic Energy Commission Idaho Operations Office Reports
1
UC (Series)
1
2 More
13 Matching Results
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13
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1964
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
February 15, 1965
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Design, Construction, and Initial Operation of General Atomic In-Pile Loop
From preface: To test the HTGR fuel-element design under environmental conditions of radiation, temperature, and pressure that approximate those in the Peach Bottom core and to test the operability of a dynamic system containing a vented graphite-clad fuel element.
Date:
February 15, 1965
Creator:
Simon, R. H.
System:
The UNT Digital Library
Comparative Fuel Cycle Evaluations, Low Decontamination Pyroprocessing, and Aqueous Reprocessing: Part 2. UC Fuel in a Thermal Reactor
From abstract: Preliminary cost estimates for fuel cycles using both aqueous and CARBOX reprocessing are presented.
Date:
February 15, 1965
Creator:
Mattern, K. L. & Colby, L. J., Jr.
System:
The UNT Digital Library
Tungsten Cladding of Tungsten-Uranium Dioxide (W-UO2) Composites by Deposition from Tungsten Hexafluoride (WF6)
A program is being conducted to develop a process for cladding tungsten and tungsten cermet fuels with tungsten deposited from the vapor state by the hydrogen reduction of tungsten hexafluoride. Early work was performed using recrystallized, high purity, commercial tungsten as the substrate material. Temperatures in the range 660 to 12950F (350 to 1700°C) and pressures from 10 to 350 mm Hg were investigated. Hydrogen to WF 6 ratios of 10: 1 to 150: 1 were utilized. Efforts were directed toward optimizing deposition process parameters to attain control of qualities such as coating thickness, uniformity, density, impurity content, and surface quality. Substrate penetration methods have been investigated in the interest of completely eliminating the interface between the fueled substrate and cladding. In addition, the effects of process parameters and post-cladding heat treatments on the fuel retention properties of clad composites at 4500 degrees F (2480 degrees C) in hydrogen for 2 hours have been evaluated. As a result of work performed during the first phase of the program it has been shown that the rate of deposition of tungsten from WF 6 and the uniformity of the deposit can be varied in a predictable and reproducible manner by exercising control …
Date:
February 15, 1965
Creator:
Lamartine, J.T. & Hoppe, A.W.
System:
The UNT Digital Library
THE COMPRESSIBILITY OF GASEOUS MIXTURES OF HELIUM-NITROGEN AND HELIUM- DEUTERIUM AT HIGH PRESSURES
None
Date:
February 15, 1965
Creator:
Cramer, J.D.
System:
The UNT Digital Library
METHODS FOR CALCULATION OF THE ELK RIVER REACTOR FUEL INVENTORY
None
Date:
February 15, 1965
Creator:
Kennedy, M.L.; Ho, C. & Kendrick, E.D.
System:
The UNT Digital Library
Advanced, Graphite-Matrix, Dispersion-Type Fuel Systems And Research on Graphite. Quarterly Progress Report for the Period Ending February 14, 1965
None
Date:
February 15, 1965
Creator:
Bokros, J. C.; Goeddel, W. V.; Lonsdale, H. K.; Price, R. J.; White, J. L. & Zumwalt, L. R.
System:
The UNT Digital Library
TEMPERING BEHAVIOR OF TWO PRESSURE-VESSEL STEELS
None
Date:
February 15, 1965
Creator:
Ferrill, D.A.; DiNuzzo, L.J. & Oberdick, R.H.
System:
The UNT Digital Library
ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. Quarterly Progress Report, October 1-December 1964
None
Date:
February 15, 1965
Creator:
unknown
System:
The UNT Digital Library
REPETITIVELY PULSED ACCELERATOR BOOSTERS
None
Date:
February 15, 1965
Creator:
Beyster, J.R. & Russell, J.L.
System:
The UNT Digital Library
USE OF NEUTRON ACTIVATION ANALYSIS IN SCIENTIFIC CRIME DETECTION. 12- Month Summary Report for the Period November 1, 1963-October 31, 1964
None
Date:
February 15, 1965
Creator:
Bryan, D.E. & Guinn, V.P.
System:
The UNT Digital Library
Technical feasibility of using uranium oxide fuels at Hanford
The use of uranium oxide fuel and the dispensing with metallic fuel elements in the Hanford production reactors have been contemplated in the past but have not been examined in any detail. This report reviews the technical feasibility of using oxide fuel and discusses the reactor limitations and changes in plutonium and isotope production. These results are based on preliminary calculations and a research and development program would be required to establish the validity of the calculated values. The research and development program is estimated to require $3.6 million over a three-year period. Technical aspects of using oxide are discussed in general for N, K, and the smaller reactors. The variations in uranium-to-graphite weight ratio and operating conditions vary the limitations encountered with each reactor type with an oxide fuel cycle. Plutonium separation and uranium oxide recycle on site have been examined, and a technical review of the limitations and the additional process requirements are presented.
Date:
February 15, 1965
Creator:
unknown
System:
The UNT Digital Library
Lithologic Log of the U12g.06-U1 Core Drill Hole, Area 12, Nevada Test Site
The following report presents the lithologic log of the description of the tuff penetrated by the U12g.06-U1 core drill hole located at the end of the U12g main tunnel at the Area 12, Nevada Test Site.
Date:
February 15, 1965
Creator:
Emerick, W. L.
System:
The UNT Digital Library