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The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel

Report containing experimental data testing the hypothesis that aluminum reactor tubes were "the site of most radioisotope production in the deionized water cooled system" and that zirconium tubes provided "only nominal participation" (p. 2).

Date: October 1964

Creator: Silker, W. B. & Thomas, C. W.

Partner: UNT Libraries Government Documents Department

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The H-4, H-5, and H-6 Irradiation Experiments: Irradiation of N-Reactor Graphite, Interim Report Number 1

Report regarding an experimental program by Hanford Laboratories' in order "to determine the long-term irradiation behavior of the graphite used as the moderator in N-Reactor. The primary objectives of the program are to provide data for predictions of the distortion of the N-Reactor moderator and the stress conditions which could arise from the difference in the the rate and extent of contraction between the transverse and parallel orientations of the graphite bars" (p. 1).

Date: October 1964

Creator: Helm, J. W.

Partner: UNT Libraries Government Documents Department

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Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements

Report containing supplementary material for "Plutonium Recycle Critical Facility, Final Safeguards Analyses." This material expands upon previously supplied safety information and resolves previously unreviewed safety questions. Appendix begins on page A.1.

Date: October 1964

Creator: Swanberg, F.

Partner: UNT Libraries Government Documents Department

open access

6144-Channel Time-of-Flight Analyzer

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.

Partner: UNT Libraries Government Documents Department

open access

Analog Computer Simulation of a Pulsed Extraction Column

Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).

Date: September 1964

Creator: Benham, R. D. & Wilburn, N. P.

Partner: UNT Libraries Government Documents Department

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

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.

Partner: UNT Libraries Government Documents Department

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The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2

Report documenting "the long-term irradiation stability of the graphite used as the moderator in the Experimental Gas Cooled Reactor (EGCR) at Oak Ridge" (p. 1) by irradiating capsules at the General Electric Test Reactor. This includes the design and construction of the experiment, experiment procedures, and results of irradiation. Appendices begin on page 83.

Date: September 1964

Creator: Helm, J. W.

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

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.

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

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.

Partner: UNT Libraries Government Documents Department

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Recovery of Aluminum Nitrate Nonahydrate from Redox Acid Waste, Part 1: Computer Study

Report describing an analog computer simulation of a counter-current crystallization process for use in the recovery of aluminum nitrate nonahydrate from redox acid waste

Date: July 1964

Creator: Godfrey, W. L. & Benham, R. D.

Partner: UNT Libraries Government Documents Department

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Standardization and Evaluation of Grain Size Test for Uranium Fuel

Report that "describes the selection of "standard fuel cores for calibrating an ultrasonic tester designated UT-2C" (p. 3) at Hanford Laboratories.

Date: July 1964

Creator: Spice, R. D.

Partner: UNT Libraries Government Documents Department

open access

Thin Wall Tubing Tests Using Ultrasonic Shear Waves: Part 2 - Production Test Equipment, Its Operation and Test Results

Report describing Hanford Laboratories' second report regarding thin wall tubing tests. This part covers "the production [of] test equipment developed, its operation, and test results" (p. 2).

Date: June 30, 1964

Creator: Zeutschel, M. F. & Dixon, N. E.

Partner: UNT Libraries Government Documents Department

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Graphite Burnout Monitoring: Part 1, Monitor Preparation and Handling Techniques

Report that describes graphite oxidation monitors and their proper storage and handling, as well as the losses encountered when moving the monitors between the laboratory and the reactor.

Date: June 1964

Creator: Ryan, B. A.

Partner: UNT Libraries Government Documents Department

open access

A New Model Concept for Large Nuclear Reactors

Report regarding the computer assisted model for a large nuclear reactor. This includes formulas and relevant procedures.

Date: June 1964

Creator: Harvey, R. A.

Partner: UNT Libraries Government Documents Department

open access

Welding Plutonium-Containing Fuel Elements

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.

Partner: UNT Libraries Government Documents Department

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Fretting Corrosion in the Plutonium Recycle Test Reactor

Report that summarizes out-of-reactor tests undertaken to determine operating conditions, estimate damage from and extent of fretting corrosion, and describe continuing tests planned to monitor and eliminate this corrosion.

Date: March 1964

Creator: Winegardner, W. K.

Partner: UNT Libraries Government Documents Department

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Solvent Extraction of Strontium, Cerium, and are Earths with D2EHPA, Part 2: Pilot Plant Studies

Report that "presents the results of pilot plant studies on the application of the D2EHPA (di-2-ethylhexyl phosphoric acid) solvent system to the needs of the Hanford Waste Management Program" (p. 1).

Date: February 1964

Creator: Richardson, G. L.

Partner: UNT Libraries Government Documents Department

open access

Hanford Graphite Superheat Reactor (HGSR) Design Study and Evaluation

Report containing the results of a preliminary study of a design concept for a graphite-moderated pressure tube reactor. Topics include reactor design, operating procedures, subsystems, hazards analysis, and economic potential. Appendices begin on page 174.

Date: January 1964

Creator: Hanford Atomic Products Operation. N-Reactor Project Section.

Partner: UNT Libraries Government Documents Department

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Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor

Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107.

Date: December 9, 1963

Creator: Aase, D. T.; Fox, J. C.; Hennig, R. J.; Peterson, R. E.; Stewart, S. L. & Toyoda, K. G.

Partner: UNT Libraries Government Documents Department

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In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 3, July 1963 - November 1963

Report containing the results of a two year program wherein the 85 zircaloy-2 pressure tubes in Hanford Laboratories' Plutonium Recycle Test Reactor (PRTR) were monitored. Experimental procedures and results are described.

Date: December 1963

Creator: Pankaskie, P. J.

Partner: UNT Libraries Government Documents Department

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Irradiation Behavior of High Purity Uranium

Report that "describes the behavior of small, high purity uranium specimens irradiated under controlled conditions" (p. 2).

Date: November 1963

Creator: Leggett, R. D.; Mastel, B. & Bierlein, T. K.

Partner: UNT Libraries Government Documents Department

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Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium

Report regarding "the development of a process suitable for large-scale separation of highly purified promethium from the trivalent fission product rare earth mixture" (p. 3).

Date: October 1963

Creator: Wheelwright, E. J. (Earl J.) & Roberts, F. P.

Partner: UNT Libraries Government Documents Department

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A Method for Beta-Gamma Hand and Shoe Counting Under Varying Background Conditions

Report containing a method for beta-gamma counting of hands, shoes, and clothing via an instrument that employs scintillation detectors and solid-state circuits.

Date: October 1963

Creator: Spear, W. G.

Partner: UNT Libraries Government Documents Department

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Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M)

Report containing the dimensions, materials, and fabrication details for swage compacted, mixed oxide (UO2-PuO2), fuel elements for the Plutonium Recycle Test Reactor (MARK I-M).

Date: October 1963

Creator: Hanford Atomic Products Operation

Partner: UNT Libraries Government Documents Department

62 Matching Results

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The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel

The H-4, H-5, and H-6 Irradiation Experiments: Irradiation of N-Reactor Graphite, Interim Report Number 1

Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements

6144-Channel Time-of-Flight Analyzer

Analog Computer Simulation of a Pulsed Extraction Column

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

The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2

Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies

Progress in Nondestructive Testing: A Summary of Hanford Achievements in These Programs Under General Electric, 1952 - 1964

Recovery of Aluminum Nitrate Nonahydrate from Redox Acid Waste, Part 1: Computer Study

Standardization and Evaluation of Grain Size Test for Uranium Fuel

Thin Wall Tubing Tests Using Ultrasonic Shear Waves: Part 2 - Production Test Equipment, Its Operation and Test Results

Graphite Burnout Monitoring: Part 1, Monitor Preparation and Handling Techniques

A New Model Concept for Large Nuclear Reactors

Welding Plutonium-Containing Fuel Elements

Fretting Corrosion in the Plutonium Recycle Test Reactor

Solvent Extraction of Strontium, Cerium, and are Earths with D2EHPA, Part 2: Pilot Plant Studies

Hanford Graphite Superheat Reactor (HGSR) Design Study and Evaluation

Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor

In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 3, July 1963 - November 1963

Irradiation Behavior of High Purity Uranium

Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium

A Method for Beta-Gamma Hand and Shoe Counting Under Varying Background Conditions

Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M)