UNT Libraries Government Documents Department - 36 Matching Results

Search Results

Results: 1 - 24 next
open access

PM-1 Nuclear Power Plant Program: 4th Quarterly Progress Report, December 1, 1959-February 29, 1960

Description: From abstract: The principal efforts during the fourth project quarter were the near-completion of the final design and preparation of specifications for plant components. Reactor development work included final preparations for the flexible zero-power test (PMZ-1) program and revised fuel element irradiation test program, continuation of reactor flow test, further work on heat transfer test program, and final design and fabrication of the prototype magnetic jack-type control rod actuators.
Date: April 5, 1960
Creator: Martin Company. Nuclear Division.
open access

PM-1 Nuclear Power Plant Program: 5th Quarterly Progress Report, March 1, 1960-May 31, 1960

Description: From abstract: Reactor development work includes: initiation of the flexible zero-power test (PMZ-1) experimental program, fabrication and delivery of a PM-1 type fuel element, continuation of reactor flow and heat transfer tests, development work on rare earth control rods, and testing and redesign of the prototype magnetic jack-type control rod actuator.
Date: July 5, 1960
Creator: Martin Company. Nuclear Division.
open access

PM-1 Nuclear Power Plant Program: Final Progress Report, September 1, 1962 Through Completion

Description: From abstract: The principal efforts during the final period were concerned with plant testing, modifications to the plant to enable it to produce full design load at high ambient temperatures, the compilation and evaluation of plant performance data, preparation of documents and transfer of the plant to the AEC and final resolution of all outstanding contract scope items.
Date: July 15, 1963
open access

Special Welding Techniques : Final Summary Report

Description: From foreword: This is the final report on Special Welding Techniques. The work of the third and final year is discussed in detail, and the accomplishments of the first two years are summarized.
Date: January 1957
Creator: Mueller, John; Maxwell, William & Siltanen, James
open access

Proceedings of the ANPP Reactor Analysis Seminar, October 11 and 12, 1960

Description: From foreword: Seminar to afford personnel associated with work in the field of reactor analysis within the various programs an opportunity to more thoroughly acquaint themselves with current activities and experience throughout the ANPP.
Date: January 1961
Creator: O'Brien, J. F.
open access

ANPP Code Development Program: An Experimental Program on Water-Moderated Arrays of Uranium and Stainless Steel

Description: From summary: This report describes an experimental study performed on critical arrays of water-moderated, flat plate, laminated fuel bundles. The experiments were performed in support of analytical studies undertaken in the ANPP Code Development Program. The fuel bundles were built up using fully enriched uranium metal foils, stainless steel plates and boron stainless steel plates.
Date: May 1962
Creator: Welshans, L.
open access

Development of Iron-Aluminum Base Alloys for Gas Cooled Reactor Components: Second Quarterly Progress Report, June 1958

Description: From summary: Description of a program undertaken to develop an iron-aluminum base alloy for service approaching 1600 degrees Fahrenheit. The program includes development of an alloy, development of techniques for fabricating fuel elements, reprocessing investigations and irradiation testing of iron-aluminum base alloys.
Date: June 1958
Creator: Mueller, J.
open access

PM Research and Development Task 1.0 : Core 2 Final Design Report

Description: From summary: This report describes the final design of Core 2, which is being developed primarily as a replacement core for the PM-1 and PM-3A nuclear power plants. In addition, the thermal and hydraulic capabilities were investigated; these indicate applicability of the core to higher powered PM-type plants.
Date: April 1963
Creator: Russo, F.; Brittain, W.; Lightner, R. & Baer, R.
open access

Development of Iron-Aluminum Base Alloy for Gas Cooled Reactor Components: Final Report

Description: From summary: Description of an iron-aluminum-chromium alloy, DB-2, used as the starting point of a program initiated to develop an iron-aluminum base alloy for cladding gas-cooled reactor core components. Secondary aims were to gain knowledge of fuel element fabric-ability, radiation effects and acid solubility of iron-aluminum base alloys.
Date: April 1959
Creator: Tate, Frank
open access

Fluidized Bed Reactor Study: Phase I - Feasibility

Description: From abstract: The Fluidized Bed Reactor (FBR) consists of a bed of fuel pellets which circulate in a confined core region as the result of the upward flow of fluid through the particles. In the present concept the fluid acts as a fluidizing, coolant and reactor moderator medium. This report is the results of the Phase I study to determine the feasibility of this concept.
Date: February 1959
open access

Feasibility Study of Water-Cooled Thermionic Nuclear Power Plant

Description: From introduction: Feasibility of the thermionic reactor system determined by a comparison of plant features such as component and plant reliability, capital and operating costs, and the number of air-transportable modules required, to existing portable nuclear power plants.
Date: November 1962
Creator: Martin Company. Nuclear Division.
open access

PM-3A Nuclear Power Plant Program

Description: From summary: Progress report on the production of detailed piping and equipment installation drawings for the PM-3A nuclear power plant program. Attention has been paid to the procurement of those valves and specialty items associated with the piping system.
Date: July 21, 1961
Creator: Martin Company. Nuclear Division.
open access

ANPP Code Development Program Pressurized Water Task Quarterly Progress Report: Number One, November 1959

Description: From introduction: The objective of this program is the development of a nuclear physical model and its calculation code for pressurized-water cooled and moderated reactors to predict accurately reactivity, rod positions and power distributions at operating temperatures, and reactor life from a nuclear standpoint.
Date: November 1959
Creator: Olsen, T. M.; Welshans, L. & Eicheldinger, C.
open access

Final Safety Analysis: Ten-Watt Strontium-90 Fueled Generator for an Unattended Light Buoy, SNAP-7A

Description: From introduction: A prototype Strontium-90 fueled generator will be used to fulfill the power requirements of an unattended automatic light buoy...Primary objectives are to provide continuous absolute containment of the radiostrontium fuel...and biological shielding of the direct radiation from the heat source.
Date: February 1962
Creator: Brooks, Phillip M. & Keegan, James J.
open access

Final Safety Analysis: Ten-Watt Strontium-90 Fueled Generator for an Unattended Meteorological Station, SNAP-7C

Description: From introduction: The primary objectives in designing a nuclear safe radiostrontium generator are: continuous absolute containment of the radiostrontium fuel, which is a relatively insoluble and chemically stable fuel compound, and biological shielding of the direct radiation from the heat source. This report evaluates the safety aspects of a prototype Strontium-90 fueled generator which will be utilized by the U.S. Navy to power and unattended automatic meterological station.
Date: 1962
Creator: Brooks, Phillip M. & Keegan, James J.
open access

Upper Atmosphere Re-entry Study High Altitude Burnup: Volume 2

Description: From summary: This report broadly reviews several methods of determining the fate of radioactive fuels (in space power units) burned up on re-entry into the earth's atmosphere.
Date: 1961?
Creator: Harvey, Douglas G. & Brooks, Phillips M.
open access

Swaged Metal Fiber-UO₂ Fuel Element: Final Report

Description: From introduction: The objectives of this program were to: study the variables of uranium dioxide, metal fibers and cladding material and determine the effects of swaging, develop thermal conductivity tests for small diameter rod-type elements, determine the thermal conductivity of various combinations of metal fibers and uranium dioxide, and select optimum combinations of the above variables to recommend for irradiation testing.
Date: January 1960
Creator: Kane, John
open access

Strontium 90 Power Project: Final Summary Report

Description: From summary: The primary purpose of this project is to determine the feasibility of converting reactor waste Strontium-90 into a safe and useful source of electrical energy. Secondary purpose is physical and environmental testing of the power conversion device or thermoelectric couples. This required actual fabrication of a 100-thermal-watt strontium titanate fuel element
Date: March 1960
Back to Top of Screen