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An evaluation of simple iron-water radiation shields and radiation measurements within concrete-lined and -capped pits

Description: Program 3 of Operation BREN consisted in a study of the performance of biological shields composed of various arrangements of steel, water, and borated polyethylene in spherical, cubical, and parallelepipedal geometries. Studies were also made of the radiation levels within concrete-lined and -capped pits, 4 ft in dia and 8 ft deep. The principal radiation source was the ORNL Health Physics Research Reactor, an unshielded, unreflected, 90 wt % U-10 wt % Mo, cylindrical bare-metal assembly. It w… more
Date: July 31, 1964
Creator: Muckenthaler, F. J.; Jung, L.; Blosser, T. V.; Freestone, R. M. Jr. & Miller, J. M.
Partner: UNT Libraries Government Documents Department
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Irradiated Fuel Age Determination Study

Description: The release of uncontrollable quantities of harmful fission products such as I{sub 131} upon processing areas. At present this is done by procedural techniques using cards, filing techniques, and cross checks. These methods are entirely independent of the characteristics of the fuel itself and are subject to failure from human error. It is therefore advantageous to find a method of determining the age of irradiated fuel after discharge from the properties of the fuel. Such a method, with its re… more
Date: August 31, 1964
Creator: Cooley, D. E.
Partner: UNT Libraries Government Documents Department
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Research and Engineering, N-Reactor Department monthly record report

Description: During the major part of October the N-Reactor was shut down for dump condenser repair, scheduled maintenance and equipment modifications. Work on dump condensers was successfully completed and the construction and tie-in of steam generator cell No. 4 was accomplished. Power ascension was initiated on October 24 and the N-Reactor in now operating with all five steam generator cells in full service. Process physics, in-plant testing, and technical activities are described in this document.
Date: October 31, 1964
Creator: Leverett, M. C.
Partner: UNT Libraries Government Documents Department
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N-Reactor shutdown for fuel rupture indications - tube 3361

Description: The N-Reactor was shutdown on July 7, 1964, due to fuel rupture indications on tube 3361. The rupture has been confirmed as a failure in the downstream inner fuel element in tube 3361 caused by a pin hole in the weld and braze metal. This document presents a historical record of the rupture indications observed prior to and following the shutdown. The operating history of tube 3361 is compared with an adjacent tube, with no abnormal conditions observed at any time. Reactor temperature and power… more
Date: July 31, 1964
Creator: Renberger, D. L.
Partner: UNT Libraries Government Documents Department
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Minutes of the meeting between Richland Operations Office and United States Public Health Service on Columbia River contamination at Richland, Washington on July 16, 1964

Description: This paper contains the minutes of a meeting on Columbia River contamination at Richland, Washington, held on July 16, 1964. The US Public Health Service sponsored the meeting and representatives from the following organizations were present: Washington State Pollution Control, Washington State Department of Health, Richlands Operations Office, AEC Headquarters, and General Electric Company. The meeting dealt with reducing the amount of effluent contributed to the Columbia River, the amount of … more
Date: December 31, 1964
Partner: UNT Libraries Government Documents Department
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U-233 production

Description: No Description Available.
Date: December 31, 1964
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department
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Safety analysis of the C-1 Loop

Description: The C-1 Loop is a small in-reactor water loop located in the 105-C Building. The loop was originally designed and constructed for nonfueled testing of the effects of reactor radiation on sample corrosion, crud deposition, and coolant radiolysis. The loop was modified in 1964 to permit the irradiation of aluminum-clad fuel elements and subsequently used for about eight months for the in-reactor testing of aluminum-clad, plutonium-aluminum fuel assemblies at high coolant temperatures and pressure… more
Date: December 31, 1964
Creator: Carlson, P. A. & Deobald, T. L.
Partner: UNT Libraries Government Documents Department
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INVESTIGATION OF THERMAL-STRESS-FATIGUE BEHAVIOR OF STAINLESS STEELS. Quarterly Progress Report No. 7, July-September 1963

Description: BS>Testing of type 304-L austenitic stainless steel was completed. Thermal-stress-fatigue testing was started on ferritic pressure-vessel steel (ASTM type A302, Grade B), and work on this alloy is approximately half completed. Test specimens of type 403 martensitic stainless steel were machined and the heat treating schedule worked out in andticipation of testing this steel. The machining of test specimens of Croloy 2 1/4 steel was also started. (auth)
Date: October 31, 1964
Creator: Horton, K. E.
Partner: UNT Libraries Government Documents Department
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High Burn-Up Tests of U-Al Fuel Elements

Description: A series of irradiation tests were performed on the High Flux Beam Reactor fuel elements. The U--Al fuel elements contained 30 to 40 wt% U and 3% Si. Burnup ranged from 20 to 50%. A summary of the results is given. (C.E.S.)
Date: October 31, 1964
Creator: Weeks, J. R.; McRickard, S. B. & Gurinsky, D. H.
Partner: UNT Libraries Government Documents Department
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