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Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model

Description: Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.
Date: September 1, 1964
Creator: Swanson, C. D.; Coughren, K. D.; Dionne, P. J. & Thieme, G. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Welding Plutonium-Containing Fuel Elements

Description: Report discussing the manual and automatic welding techniques for fuel elements containing plutonium with Zircaloy-2 aluminum, and stainless steel cladding, 0.013 to 0.0889 cm (0.005 to 0.350 in.) thick" (p. 3).
Date: June 1964
Creator: Lemon, L. C.; Ross, W. T. & Bailey, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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6144-Channel Time-of-Flight Analyzer

Description: Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
Date: September 1964
Creator: Walker, R. A. & Russell, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress in Nondestructive Testing: A Summary of Hanford Achievements in These Programs Under General Electric, 1952 - 1964

Description: Report discussing the development of Hanford Laboratories' nondestructive testing programs and a summary of their results. Programs include AlSi fuel testing, N-Reactor fuel testing, and reactor research and development.
Date: August 1964
Creator: Walker, R. A. & Russell, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies

Description: Report regarding the calcination of full level Purex and Redox waste carried out "in a remotely operated pilot plant consisting of a radiant-heat spray calciner and a pot calciner and their associated off-gas equipment" (p. 4). This contains details of the calcination, effects on the waste, and difficulties encountered.
Date: September 1964
Creator: Allemann, R. T.; Roberts, F. P. & Upson, U. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak

Description: Review of previous work is presented in addition to the results of recent studies concerning loss of primary coolant when the system is cold and pressurized and the problem of supplying adequate cooling following the injection of light water.
Date: November 15, 1960
Creator: Wittenbrock, N. G. & Muraoka, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Ultrasonic Resin Level Detector

Description: This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.
Date: January 15, 1960
Creator: Hunter, D. O. & Pleasance, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Halogen Collector Test Program

Description: 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Core Tester - UT-2

Description: Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Date: July 18, 1960
Creator: Frederick, C. L. & Waldkoetter, G. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Thermal Hydraulics Laboratory at Hanford

Description: Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49.
Date: November 1961
Creator: Batch, J. M.; Toyoda, K. G. & Hanthorn, H. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford Controlled Potential Coulometer

Description: Report describing the Hanford Laboratory controlled potential coulometer. This includes the theory behind the coulometer, details of its circuitry, and performance tests. Appendix begins on page 23.
Date: July 11, 1960
Creator: Connally, R. E. & Scott, F. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory

Description: 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C

Description: Report discussing the "equilibrium uranium distribution between an aqueous nitric acid solution and a 30 per cent by volume solution of tributyl phosphate in a hydrocarbon diluent" (p. 2). This includes the necessary equations.
Date: August 12, 1960
Creator: Wilburn, N. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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