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Current status -- Second generation process tube internal corrosion

Description: Seven water leaks during the past year because of internal corrosion of second generation process tubes have emphasized the need for additional corrosion information. Numerous out-of-pile and probolog examinations have been made to determine the nature of the corrosion, and mixer fuel elements currently are charged in central zone tubes in order to reduce the corrosion rates. This document presents the data obtained to date as a general description of the tube condition at the time when the mix… more
Date: June 22, 1960
Creator: Young, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Installation of reactor gas refrigeration system -- 105-C, Project C-431

Description: It is recommended that the Design Committee approve the installation of a refrigeration system in the 105-C gas circulation system for removal of moisture from the reactor following a process tube leak as was previously approved by the C-431 Project Committed. Engineering studies show that this refrigeration system is necessary to provide sufficient water removal capacity in order that the water absorbing capacity of the system furnished by the silica gel towers will not be a limit to the rate … more
Date: March 5, 1953
Creator: Wells, H. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Manufacturing Section semiannual summary report, period ending December 31, 1966

Description: In this third semiannual issue, the reactor and power data from the Hanford Production Reactors are shown for the six-month period July through December, 1966, together with the two preceding six-month periods. Experience during the succeeding six-month period will be added in the next semiannual issue. For comparison purposes, the two years of experience will then continue to be shown by dropping and adding a six-month period with each semiannual issue.
Date: January 31, 1967
Creator: DeNeal, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Process tube expansion: 105-C conversion to self-supported fuel elements

Description: A method of reducing gas leakage and rear fate maintenance is to fix the rear gunbarrel and process tube to the shield and eliminate the need for a rear expansion bellows. This arrangement is being considered as part of the C-reactor conversion to self-supported fuel element program. The fixed rear gunbarrel will require that all hydraulic load and thermal expansion elongation of the tube be taken through the front bellows. In the event that tubes freeze in their channels, forces due to thermal… more
Date: August 9, 1961
Creator: Mollerus, F. J. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of 6.6 pH process water on process tube and fuel element corrosion

Description: Reduction of the reactor process water pH from 6.9 to 6.6 at 100-B, D, DR, KF, and H currently is proposed in order to reduce the aluminum corrosion rate and the resultant outage time for water leaks, fuel ruptures, and process tube replacement. This document reviews the current knowledge of the effect of reducing the pH to 6.6 on aluminum corrosion. An estimate of the expected costs and benefits is included.
Date: May 20, 1963
Creator: Young, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Continuous tritium effluent water monitor at the Savannah River Site

Description: A continuous monitor for tritium in water has been installed in the secondary cooling water effluent from the K-Reactor at the Savannah River Site (SRS). The monitor is designed to provide early detection of a small leak of the tritiated heavy water moderator and facilitate rapid isolation procedures. The tritium detector consists of an analysis cell containing 0.1--0.25 mm diameter beads of plastic scintillator interposed between two photomultiplier tubes and standard fast-slow coincidence ele… more
Date: November 1, 1992
Creator: Hofstetter, K. J. & Wilson, H. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Manufacturing Section semiannual summary report, period ending June 30, 1967

Description: In this fourth semiannual issue, the reactor and power data from the Hanford Production Reactors are shown for the six-month period January through June, 1967, together with data for the three preceding six-month periods. For comparison purposes, the two years of experience will continue to be shown by dropping and adding a six- month period with each semiannual issue.
Date: September 15, 1967
Creator: DeNeal, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Acoustic emission monitoring of HFIR vessel during hydrostatic testing. Final report

Description: This report discusses the results and conclusions reached from applying acoustic emission monitoring to surveillance of the High Flux Isotope Reactor vessel during pressure testing. The objective of the monitoring was to detect crack growth and/or fluid leakage should it occur during the pressure test. The report addresses the approach, acoustic emission instrumentation, installation, calibration, and test results.
Date: August 1, 1992
Creator: Friesel, M. A. & Dawson, J. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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