Evaluation of Irradiated OMRE Fuel Elements First Core Loading (open access)

Evaluation of Irradiated OMRE Fuel Elements First Core Loading

Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
Date: March 1, 1960
Creator: Walter, J. H.; Leirich, J. F. & Calkins, G. D.
System: The UNT Digital Library
OMR Degasifier Loop Experiment (open access)

OMR Degasifier Loop Experiment

Abstract: A loop has been constructed to study the removal of water and highly volatile materials from Organic Moderated Reactor coolant by vacuum degasification. An analysis of the process was made to determine the most important parameters for study during the experimental program.
Date: May 1, 1960
Creator: Corporales, G. W. & Benson, P. R.
System: The UNT Digital Library
OMRE Fuel Plate Surface Temperature Measurement (open access)

OMRE Fuel Plate Surface Temperature Measurement

Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.
Date: May 1, 1960
Creator: Sudar, S.
System: The UNT Digital Library
Plutonium: Enriched OMR Cores (open access)

Plutonium: Enriched OMR Cores

Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
Date: May 1, 1960
Creator: Connolly, T. J.
System: The UNT Digital Library
Engineering Evaluation of a Mixed Alloy Fuel Element Irradiated at Elevated Temperatures in the SRE (open access)

Engineering Evaluation of a Mixed Alloy Fuel Element Irradiated at Elevated Temperatures in the SRE

Abstract: A fuel material evaluation was made by destructively examining a full-scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/MTU.
Date: June 1, 1960
Creator: Ballif, J. L.; Hayward, B. R. & Walter, J. W.
System: The UNT Digital Library
OMRE Fuel Removal and Shipping Equipment (open access)

OMRE Fuel Removal and Shipping Equipment

Abstract: A portable assembly for handling and shipping OMRE fuel elements is described and details of its operation are given. Problems of heat transfer and radiation shielding are discussed, and detailed analysis are presented.
Date: April 1, 1960
Creator: Mallon, P. J.; Duncan, D. S. & Noyes, R. C.
System: The UNT Digital Library
Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service (open access)

Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service

Abstract: Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of commercially available valves considered for use in the sodium coolant system of the Hallam Nuclear Power Facility.
Date: May 1, 1960
Creator: Baroczy, C. J.
System: The UNT Digital Library
300,000-KWE SGR Nuclear Power Plant of Current Technology (open access)

300,000-KWE SGR Nuclear Power Plant of Current Technology

Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
Date: August 1, 1960
Creator: Renard, J.; Peckinpaugh, C. L. & Aronstein, R. E.
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1959 - March 1, 1960 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1959 - March 1, 1960

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: April 1, 1960
Creator: Hardy, Edward P., Jr. & Klein, Stanley
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1960 - June 1, 1960 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1960 - June 1, 1960

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: July 1, 1960
Creator: Hardy, Edward P., Jr.; Klein, Stanley & Rivera, Joseph
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1960 - September 1, 1960 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1960 - September 1, 1960

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: October 1, 1960
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System: The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Third Quarter, January-March 1960 (open access)

Nuclear Superheat Quarterly Project Report: Third Quarter, January-March 1960

From introduction: "This is the third of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: July 1, 1960
Creator: Pennington, R. T.
System: The UNT Digital Library
Automatic Control of T7 Tanker Boiling Water Reactor Propulsion System: Preliminary Design and Economic Evaluation (open access)

Automatic Control of T7 Tanker Boiling Water Reactor Propulsion System: Preliminary Design and Economic Evaluation

From introduction: "This report sets forth the results of a technical and economic analysis of automatic propulsion system control as a possible design improvement in the direct cycle boiling water reactor propulsion system in a T7 tanker."
Date: September 1, 1960
Creator: U.S. Atomic Energy Commission
System: The UNT Digital Library
Halogen Collector Test Program (open access)

Halogen Collector Test Program

Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date: March 1, 1960
Creator: Arthur D. Little, Inc.
System: The UNT Digital Library
Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory (open access)

Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory

Report that summarizes the potential hazards of the Hanford Critical Mass Laboratory and presents operation procedures which will limit the probability of a nuclear accident. The report also outlines the planned experimental program, descriptions of the facility, and the administration of nuclear safety in the laboratory.
Date: August 1, 1960
Creator: Reardon, W. A.; Clayton, E. D.; Brown, C. L.; Masterson, R. H.; Powell, T. J.; Richey, C. R. et al.
System: The UNT Digital Library