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Columbia River Thermal Effects Study. Quarterly progress report, January--March 1969

Description: The Columbia River Thermal Effects Study is an interagency study being carried out jointly by the Atomic Energy Commission, the Federal Water Pollution Control Administration, and the Bureau of Commercial Fisheries. Leadership for the study as a whole has been assigned to the Northwest Region of the FWPCA. By agreement among the participating agencies, a brief progress report on each project of the study is to be provided each quarter to the FWPCA on a standardized format. The FWPCA consolidate… more
Date: March 31, 1969
Creator: Foster, R. F. & Nakatani, R. E.
Partner: UNT Libraries Government Documents Department
open access

Abstract -- A description of low temperature hydriding of zircaloy at Hanford

Description: The two K Reactors at the Hanford Plant of the Atomic Energy Commission were retubed in 1963 with ribless Zircaloy process tubes. These tubes, 1.81 inch OD x 0.037 inch wall, were made by tube reducing methods from extruded blooms and were installed without final pickling or autoclaving. These tubes are used with once-through filtered water with a maximum coolant temperature of approximately 110 C. After approximately two years` service, it was discovered that these tubes were absorbing hydroge… more
Date: March 31, 1966
Creator: Alexander, W. K.
Partner: UNT Libraries Government Documents Department
open access

Transfer measurement statistic derived from Purex processing measurements` quality control program, second half of 1965

Description: This report gives an analysis of the audit data obtained during the last half of 1965 at eight transfer stations: L9 plutonium product, K6 uranium product, F15 salt waste, D5 dissolved feed, F18 utility waste, G8 organic wash waste, R8 organic wash waste, and U3 laboratory waste. Two ways of improving the Purex quality control program are described.
Date: March 31, 1966
Creator: Hough, C. G.
Partner: UNT Libraries Government Documents Department
open access

710 reactor program, progress report No. 13

Description: Declassified 4 Sep 1973. Information on the development of the 710 Reactor is presented concerning the performance testing of refractory-metal fuel elements, critical experiment mockup of 710 Reactor, reactor component design and development, and test facilities and pilot loop design, (DCC)
Date: March 31, 1965
Partner: UNT Libraries Government Documents Department
open access

Criticality Predictions in the Hanford Reactors

Description: The purpose of this study was to examine the general area of criticality prediction errors at the smaller (``pre-K``) reactors. Such errors evolve from a number of uncertainties which are difficult if not impossible to eliminate with present measuring and accounting techniques; the magnitude of these uncertainties in aggregate was indicated in an earlier study about 1.5 milli-k, which, at the time of the study, represented an ``inherent`` prediction error that constituted a practical limit on a… more
Date: March 31, 1965
Creator: Skidmore, S. M. & Bowers, C. E.
Partner: UNT Libraries Government Documents Department
open access

CARBIDE FUEL DEVELOPMENT. Phase IV Report, September 15, 1961-September 30, 1962

Description: Single-phase solid solution UC-- PuC powders were prepared by the carbon reduction of a mixture of UO/sub 2/ and PuO/sub 2/. A simple method was developed to determine the completion of the reaction by analyzing the exhaust gas from the furnace for CO. Four groups of solid solution (U/sub 0.8/Pu/sub 0.2/ )C/sub 0.95/ pellets were prepared for irradiation tests. The groups differed in the enrichment of uranium and in the presence or absence of nickel sintering aid. Without sintering aid, densiti… more
Date: March 31, 1963
Creator: Taylor, K.; Anderson, J. & Strasser, A.
Partner: UNT Libraries Government Documents Department
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