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20,000 KW Nuclear Power Plant Study for United States Atomic Energy Commission (open access)

20,000 KW Nuclear Power Plant Study for United States Atomic Energy Commission

Introduction: In September of 156, Gilbert Associates, Inc., entered into a contract with the United States of America, acting through the United States Atomic Energy Commission, for the study and preliminary design of a nuclear power plant being considered for integration into a central station power system at an overseas site.
Date: July 7, 1957
Creator: Gilbert Associates, Inc.
System: The UNT Digital Library
A 37,500 KW Power Reactor with Competitive Possibilities (open access)

A 37,500 KW Power Reactor with Competitive Possibilities

The following report follows the study on economics of nuclear power generation using a light water reactor.
Date: February 26, 1954
Creator: Thompson, W. I. & Cohen, Karl
System: The UNT Digital Library
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 1 (open access)

1000-MWe LMFBR Follow-On Study, Task I Report: Volume 1

From introduction: "The objective of this study is to provide information that will assist the Atomic Energy Commission in furthering the National Liquid Metal Fast Breeder Reactor (LMFBR) Program. We plan to accomplish this end, in part, by extending the original studies to include system and component design and parametric evaluations of the nuclear steam supply system and its related systems and subsystems based on an estimation of the state of technology in 1980."
Date: June 1967
Creator: Goulding, B. J.
System: The UNT Digital Library
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 2, Concept I System Description (open access)

1000-MWe LMFBR Follow-On Study, Task I Report: Volume 2, Concept I System Description

From introduction: "This report has been prepared in conjunction with the Liquid Metal Fast Breeder Reactor (LMFBR) Follow-On Study. It is the Concept I description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On Study Program."
Date: April 1967
Creator: Boyer, R. L.
System: The UNT Digital Library
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 5, Concept IV System Description (open access)

1000-MWe LMFBR Follow-On Study, Task I Report: Volume 5, Concept IV System Description

From introduction: "The last of four designs to be developed by Babcock & Wilcox (B&W), Concept IV observes ground rules established under the LMFBR Follow-On Program and is based on the estimated state of technology in 1980."
Date: August 1967
Creator: Goulding, B. J.
System: The UNT Digital Library
6144-Channel Time-of-Flight Analyzer (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.
System: The UNT Digital Library
Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report (open access)

Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report

This report describes the circumstances leading to the accident, attempts to reconstruct the nuclear reactivity conditions, and reviews the dosimetric means and results which were used to help determine the exposure of affected employees.
Date: September 12, 1958
Creator: Patton, F. S.; Bailey, J. C.; Callihan, A. D.; Googin, J. M.; Jasny, G. R.; McAlduff, H. J. et al.
System: The UNT Digital Library
Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core (open access)

Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core

From abstract: "explain all important features pertaining to a new pulsed irradiation reactor, the Capsule Driver, Core, and to analyze the potential problems and hazards of operating this reactor in the existing Spert IV facility."
Date: February 1965
Creator: Miller, R. W.; McCardell, Richard K. & Lagier, T. F.
System: The UNT Digital Library
Advanced Pressurized Water Reactor Study [Part 1]: Phase 1 Report (open access)

Advanced Pressurized Water Reactor Study [Part 1]: Phase 1 Report

From preface: This report covers Phase I of the authorized work, consisting of determination of the specific reactor concept and size for the most economic reactor, preparation of a reference design of the most promising concept and estimated capital and generating costs, evaluation of the variations in cost as a function of unit size, and evaluation of the reductions in ultimate costs for a power station having multiple units of the same type.
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
System: The UNT Digital Library
Advanced Pressurized Water Reactor Study [Part 1, Supplement]: Phase 2--A Report (open access)

Advanced Pressurized Water Reactor Study [Part 1, Supplement]: Phase 2--A Report

From introduction: This report details the progress of the Advanced Pressurized Water Reactor Study.
Date: February 1960
Creator: Stone and Webster Engineering Corporation
System: The UNT Digital Library
Advanced Pressurized Water Reactor Study [Part 3]: 235 Mw Coal-fired Generating Plant (open access)

Advanced Pressurized Water Reactor Study [Part 3]: 235 Mw Coal-fired Generating Plant

"This study is one of four initiated in 1958 by the Division of Reactor Development, U.S. Atomic Energy Commission, to assess the feasibility of power generation through the use of certain types of nuclear reactors. These studies are available from the Office of Technical Services, U.S. Department of Commerce, Washington 25, D.C."
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
System: The UNT Digital Library
Advanced Test Reactor Burnout Heat Transfer Tests (open access)

Advanced Test Reactor Burnout Heat Transfer Tests

From abstract: "Results of burnout test to determine the limiting heat flux in a simulated Advanced Test Reactor fuel element channel."
Date: January 1964
Creator: Croft, M. W.
System: The UNT Digital Library
Advanced Test Reactor: Final Shielding Design Report (open access)

Advanced Test Reactor: Final Shielding Design Report

From abstract: "This report has been prepared as a design reference document describing the calculation methods and engineering results for shielding analysis work done during the design of the Advanced Test Reactor."
Date: December 1963
Creator: Howard, J. O. & Jacks, G. M.
System: The UNT Digital Library
Advanced Test Reactor Servo Regulator Rod Test Program (open access)

Advanced Test Reactor Servo Regulator Rod Test Program

From abstract: "Verify rod mechanism characteristics reported by the United Shoe Machinery Corporation, demonstrate that rod mechanism characteristics were compatible with reactor kinetics and that over-all reactor system behavior was stable, and to recommend system modifications needed for satisfactory performance."
Date: February 1964
Creator: Pickett, R. T., III
System: The UNT Digital Library
Advanced Test Reactor Turbo Report (open access)

Advanced Test Reactor Turbo Report

From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."
Date: January 1964
Creator: Turner, Robert A.
System: The UNT Digital Library
AEC Hot Cells and Related Facilities (open access)

AEC Hot Cells and Related Facilities

Foreward: The primary purpose of this report is to present as an accumulation of basic information on the hot cells constructed to date by the United States Atomic Energy Commission.
Date: May 1958
Creator: Fosdick, Ellery R.
System: The UNT Digital Library
Aerospace Nuclear Safety: October 1 - 4, 1963 (open access)

Aerospace Nuclear Safety: October 1 - 4, 1963

Proceedings on aerospace nuclear safety.
Date: October 1963
Creator: Sandia Corporation. Technical Information Division III.
System: The UNT Digital Library
Aircraft Reactor Test Removal and Disassembly (open access)

Aircraft Reactor Test Removal and Disassembly

Report documenting the dissection of a reactor called the Aircraft Reactor Test (ART). Includes the removal of the reactor from its test cell, component removal, and plans for a for a disassembly building facility.
Date: 1960?
Creator: Abbatiello, A. A. & McQuilkin, F. R.
System: The UNT Digital Library
An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2 (open access)

An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2

Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.
Date: June 2, 1958
Creator: Spear, W. G.
System: The UNT Digital Library
An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel (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.
System: The UNT Digital Library
Ames Laboratory Annual Summary Research Report in Metallurgy: 1960 (open access)

Ames Laboratory Annual Summary Research Report in Metallurgy: 1960

Annual summary documenting research related to metallurgy at Ames Laboratory. Discussions are given of developments in the following areas: the preparation and purification of metals; phase equlibria and thermodynamic properties of alloys; physical and mechanical properties of metals and alloys; solid state studies; separation processes; and investigations dealing with diffusion, oxidation, and reduction, halide reactions, preparations, vapor pressure measurements, and transport reactions. (B.O.G.)
Date: December 1960
Creator: Ames Laboratory
System: The UNT Digital Library
Analog Computer Simulation of a Pulsed Extraction Column (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.
System: The UNT Digital Library
Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model (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.
System: The UNT Digital Library
Analysis of Failure of Type 304 Stainless Steel Clad Swaged Powder Fuel Assembly (open access)

Analysis of Failure of Type 304 Stainless Steel Clad Swaged Powder Fuel Assembly

From introduction: "The purpose of this report is to describe the observations made during the post-irradiation examination of HPD-2S, and to discuss possible modes of failure.
Date: October 3, 1963
Creator: Lees, E. A.
System: The UNT Digital Library