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Control Design Review of P&W Quarterly for July-September, 1960
This report addresses the control design review of P&W quarterly for July to September 1960.
Date:
December 5, 1960
Creator:
Proffitt, S. H.
System:
The UNT Digital Library
Research Study on Neutron Interactions in Matter as Related to Image Formation
Report discussing a study on neutron detection schemes and the effect of neutron scattering on neutron image formation quality.
Date:
December 5, 1960
Creator:
Watts, H. V. & Stone, C. A.
System:
The UNT Digital Library
FAST FLUX TEST FACILITY CONCEPTUAL SYSTEM DESIGN DESCRIPTION FOR THE HEATING AND VENTILATION SYSTEM NO. 25
The Heating and Ventilation System provides the atmospheric conditions in FFTF as required to assure that plant objectives can be met in a safe and practical manner. Included are functions and design requirements, a physical description of the system, safety considerations, principles of operation, and maintenance principles.
Date:
December 5, 1969
Creator:
unknown
System:
The UNT Digital Library
Technical data-experimental and nuclear grade graphite
This document consists of length and annealing data sheets.
Date:
December 5, 1960
Creator:
Jervis, A. J. Jr.
System:
The UNT Digital Library
Production test IP-638-D, operation of KER-1 -2, -3, and -4 simulating N reactor conditions December 5, 1963
The objective of this production tests is to irradiate N Reactor prototype and candidate fuel components and alternate products at simulated N-Reactor pressure and temperature conditions in KER Loops 1, 2, 3, and 4.
Date:
December 5, 1963
Creator:
Neidner, R.
System:
The UNT Digital Library
FAST FLUX TEST FACILITY CONCEPTUAL SYSTEM DESIGN DESCRIPTION FOR THE RADIOACTIVE WASTE SYSTEM No. 24
The FFTF Radioactive Waste System provides the equipment and facilities required for the routine collection, transfer, storage, and disposal of radioactive liquid and solid wastes. Radioactive solid wastes and radioactive liquid wastes not normally piped t o the Radioactive Waste System Receiving tanks, are packaged inappropriate containers by the systems generating the waste for collection and disposal by the Radioactive Waste System. Included are functions and design requirements, a physical description of the system, safety considerations, principles of operation, and maintenance principles.
Date:
December 5, 1968
Creator:
unknown
System:
The UNT Digital Library
Status of irradiations performed by Fuel and target irradiation technology for BNW as of November 30, 1969
This document presents details about the status of irradiations performed by Fuel and Target Irradiation Technology for BNW as of November 30, 1969.
Date:
December 5, 1969
Creator:
Barker, L. V.
System:
The UNT Digital Library
Strontium Sorption Studies Using Naturally Occurring Ion Exchange Materials
Four naturally occurring materials, namely, vermiculite, variscite, Tennessee rock phosphate, and Florida pebble phosphate, were studied to determine the feasibility of their use in columns for the sorption of strontium from high pH, intermediate-level wastes produced at ORNL. Excepting vermiculite, all materials were found to be effective in strontium removal.
Date:
December 5, 1960
Creator:
Thomas, K. T.; Jacobs, D. G.; Tamura, T. & Struxness, E. G.
System:
The UNT Digital Library
A Transport Calculation of the HFIR Beam Hole Currents
An estimate was made of the beam hole currents to be expected from both the radial and tangential beam holes in the present HFIR design. The angular fluxes required for these calculation were determined by an 18-group, S8 transport calculation (SNG reactor code). Both type beam holes produced thermal neutron currents of 7.5 x 10^10 neutrons/cm^2 sec. at a power level of 100 Mw. The nonthermal component of the beam current was 7.0 x 10^10 and 4.5 x 10^10 neutrons/cm^2 -sec for the radial and tangential holes, respectively.
Date:
December 5, 1960
Creator:
Claiborne, H. C. & Rakavy, G.
System:
The UNT Digital Library
Fabrication of Zirconium Alloys For Specific Zirconium Alloy Design Program
The raw materials and fabrication procedures employed in preparing thirty two zirconium alloy compositions for evaluation as described in GEAP-3979 are reported. Considerations involved in the extension of reported laboratory procedures to larger scale production are discussed.
Date:
December 5, 1962
Creator:
Antony, K. C. & Jones, L. T.
System:
The UNT Digital Library