UNT Libraries Government Documents Department - 70 Matching Results

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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.

Item Type: Report

open access

An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel

Report that "describes a nondestructive tester and some of its applications in measuring 10 to 100 µg of uranium surface contamination on unirradiated, low enrichment, uranium fuel elements" (p. ii).

Date: July 1963

Creator: Jackson, C. N., Jr.

Item Type: Report

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.

Item Type: Report

open access

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.

Item Type: Report

open access

The Anodizing of Zirconium

Five continuous coatings were produced on zirconium coupons using an anodizing technique. These layers appear to be quite adherent and not subject to visible or audible failure caused by flaxion of the basis metal, Their abrasion resistance, though not investigated thoroughly, appears to be moderately good.

Date: November 3, 1953

Creator: Ray, William E.

Item Type: Report

open access

An Automatic Monitor for As76 Concentrations in Reactor Cooling Water

Report that describes the development, design, and operation of a prototype instrument meant to monitor the As76 concentration in reactor cooling water streams.

Date: April 1963

Creator: Rieck, H. G. 1922-

Item Type: Report

open access

Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs.

Date: August 1962

Creator: Hanthorn, H. E.

Item Type: Report

open access

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

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: Report

open access

Construction Completion Report: CAI-816, 100-N Reactor Plant

Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.

Date: October 15, 1964

Creator: Buckner, C. L.

Item Type: Report

open access

Corrosion Studies in Simulated N-Reactor Secondary System Water Environment

Report containing the procedures and results of tests made to determine the corrosion resistance of materials in a simulation of Hanford Laboratories' N-Reactor secondary system water environment.

Date: May 1963

Creator: Larrick, A. P.

Item Type: Report

open access

Description of the Thermal Hydraulics Laboratory at Hanford

Report describing the thermal hydraulics facilities at Hanford Laboratories as well as its operation, equipment, and systems.

Date: June 2, 1960

Creator: Batch, J. M. & Toyoda, K. G.

Item Type: Report

open access

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.

Item Type: Report

open access

A Device for Recording Fuel Element Dimension on Punched Paper Tape

Report that "describes a system for translating the position of a strip-chart recorder potentiometer shaft into decimal digital form" (p. ii).

Date: December 1962

Creator: Driver, G. E.

Item Type: Report

open access

Dissolution of Power Reactor Fuel Cores

Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials.

Date: August 26, 1960

Creator: Blaine, H. T.

Item Type: Report

open access

Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor

Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.

Date: June 1961

Creator: Harty, H.; Regimbal, J. J.; Toyoda, K. G. & Widrig, R. D.

Item Type: Report

open access

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.

Item Type: Report

open access

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.

Item Type: Report

open access

Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1

Report discussing the evaluation of the "behavior of austenitic and ferritic stainless steels, iron-chromium-aluminum base alloys and nickel-base superalloys, in medium and high temperature simulated reactor environments" (p. 2).

Date: February 1961

Creator: Pessl, H. J.

Item Type: Report

open access

Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1

Report describing the evaluation of the effects of irradiation on a high pressure water loop that ruptured while testing fuel elements. Includes photographs of the damaged tube as well as chemical analyses.

Date: December 1962

Creator: Defferdin, L. J.

Item Type: Report

open access

Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.

Date: September 1961

Creator: Kosut, B. S.; Leggett, R. D. & Marshall, R. K.

Item Type: Report

open access

Final Design Report: DR-1 Gas Loop

Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.

Date: March 1961

Creator: Baars, R. E.

Item Type: Report

open access

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.

Item Type: Report

open access

Fuel Core Tester - UT-2

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: Report

open access

Gas-Metal Reactions with Iron- and Nickel-Base Heat Resistant Alloys: An Interpretive Literature Survey

Report reviewing literature that concerns "the compatibility of stainless steels and nickel-base alloys with various gases which might be present in or around a high temperature nuclear reactor" (p. 2).

Date: May 1963

Creator: Jones, D. A.

Item Type: Report

UNT Libraries Government Documents Department - 70 Matching Results

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6144-Channel Time-of-Flight Analyzer

An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel

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 Anodizing of Zirconium

An Automatic Monitor for As76 Concentrations in Reactor Cooling Water

Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

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

Construction Completion Report: CAI-816, 100-N Reactor Plant

Corrosion Studies in Simulated N-Reactor Secondary System Water Environment

Description of the Thermal Hydraulics Laboratory at Hanford

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

A Device for Recording Fuel Element Dimension on Punched Paper Tape

Dissolution of Power Reactor Fuel Cores

Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor

Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor

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

Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1

Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1

Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Final Design Report: DR-1 Gas Loop

Fretting Corrosion in the Plutonium Recycle Test Reactor

Fuel Core Tester - UT-2

Gas-Metal Reactions with Iron- and Nickel-Base Heat Resistant Alloys: An Interpretive Literature Survey