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Fast Flux Test Facility. Design and Development Quality Assurance Requirements for the FFTF

Description: The document is presented to provide general management requirements for Pacific Northwest Laboratory (PNL) and contractor design and development quality assurance programs to assure the required quality level of the various items required for the FFTF. The document is applicable as imposed by the contract to FFTF contractors and subcontractors. The document is also applicable to PNL design and development activities related to the FFTF.
Date: October 23, 1968
Creator: Albert, W. G.
Partner: UNT Libraries Government Documents Department
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Damage Flux in Critical Assemblies

Description: An important limitation on the design of an inpile thermionic reactor is the fast neutron irradiation damage to the insulators, which is expressed quantitatively by the energy weighted neutron flux, or damage flux. The behavior of the damage flux has been investigated for a set of hypothetical critical assemblies containing different types of fuel and different amounts of moderator. It is shown that for a given fuel, the damage flux is reduced by moderating the neutron spectrum, and for a given… more
Date: October 31, 1968
Creator: Anderson, R.C.
Partner: UNT Libraries Government Documents Department
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Isotopic Power Source Development

Description: No Description Available.
Date: October 31, 1968
Creator: Beaver, R. J. & Donnelly, R. G.
Partner: UNT Libraries Government Documents Department
open access

Cryotrap Checkout Test Report

Description: This report presents the results of an evaluation of the data acquired during the checkout of the LN2 Cryotrap System, performed on 30 September 1968, and 4 October 1968.
Date: October 18, 1968
Creator: Brandt, H. W.
Partner: UNT Libraries Government Documents Department
open access

Alkali- Metal Corrosion of High- Temperature

Description: Report talking about Alkali- Metal Corrosion of High- Temperature
Date: October 31, 1968
Creator: DeVan, J. H.; Litman, A. P. & Harms, W. O.
Partner: UNT Libraries Government Documents Department
open access

Thulium oxide fuel characterization study (thulium-170 fueled capsule parametric design)

Description: A doubly encapsulated thulia wafer, i.e., individually lined wafers stacked one upon another inside a fuel capsule was studied. The temperature profiles were determined for thulia power densities ranging from 8 to 24 W/cc and fuel capsule surface temperatures ranging from 1000/sup 0/F (538/sup 0/C) to 2000/sup 0/F (1093/sup 0/C). Parametric studies were also carried out on a singly encapsulated configuration in which the thulia wafers were stacked face to face in an infinitely long, lined cylin… more
Date: October 1, 1968
Creator: DesChamps, N.H.
Partner: UNT Libraries Government Documents Department
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