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11,400 KW Nuclear Power Plant Employing an Organic Moderated Reactor: Preliminary Description
Description:
Abstract: The preliminary design is described for a small electric-power-generating plant powered by an organic moderated reactor. System and component requirements are discussed and possible design configurations and equipment are described.
Date:
1957
Creator:
Wheelock, C. W.
A 37,500 KW Power Reactor with Competitive Possibilities
Description:
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
200-Mwe Prototype Large SGR: Reactor Structure Design and Evaluation
Description:
From abstract: This document presents the reactor structure design and evaluation for a 200-Mwe prototype large SGR.
Date:
1965
Creator:
North American Aviation. Atomics International Division.
300,000-KWE SGR Nuclear Power Plant of Current Technology
Description:
Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
Date:
August 1, 1960
Creator:
Renard, J.; Peckinpaugh, C. L. & Aronstein, R. E.
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1
Description:
From introduction: "Summary report of the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company."
Date:
February 14, 1964
Creator:
General Electric Company
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2
Description:
From introduction: "Presents the detailed description of a 1000 MW Electric Power Plant employing one or two Boiling Water Reactors as the steam source."
Date:
February 14, 1964
Creator:
General Electric Company
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3
Description:
From introduction: "Contains the appendices and a complete set of drawings related to the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company for the United States Atomic Energy Commission."
Date:
February 14, 1964
Creator:
General Electric Company
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.
ABWR: PL-2 Design Report
Description:
From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
Date:
October 15, 1960
Creator:
Combustion Engineering, inc. Nuclear Division.
ABWR Design and Development Quarterly Progress Report: July 1 - September 30, 1961
Description:
Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
Date:
October 16, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962
Description:
Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
Date:
April 15, 1962
Creator:
Combustion Engineering, inc. Nuclear Division.
Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962)
Description:
The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date:
April 1, 1962
Creator:
Rider, B. F.
Accurate Nuclear Fuel Burnup Analyses; Second Quarterly Progress Report, (March - May 1962)
Description:
The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date:
July 1, 1962
Creator:
Rider, B. F.
Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report: Seventh Quarter, June 1963 - August 1963
Description:
Quarterly progress report on Accurate Nuclear Fuel Burnup Analysis project.
Date:
September 1, 1963
Creator:
Rider, B. F.; Ruiz, C. P.; Peterson, J. P., Jr.; Luke, P. S., Jr. & Smith, F. R.
Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core
Description:
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.
Adiabatic Injection
Description:
From introduction comments: The present analysis is intended to examine the relations for "adiabatic" injection in general from a different point of view.
Date:
September 22, 1955
Creator:
Linlor, William I., 1915-
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development
Description:
First part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. I-ii).
Date:
April 1962
Creator:
Combustion Engineering, inc. Nuclear Division.
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies
Description:
Second part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. II-i).
Date:
March 1962
Creator:
Combustion Engineering, inc. Nuclear Division.
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients
Description:
Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date:
October 23, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept
Description:
Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date:
October 23, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
An Advanced Sodium-Graphite Reactor Nuclear Power Plant
Description:
Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date:
March 15, 1960
Creator:
Churchill, J. R. & Renard, J.
Advanced Test Reactor Burnout Heat Transfer Tests
Description:
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.
Advanced Test Reactor: Final Shielding Design Report
Description:
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.
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Atomic Energy Commission Reports
733
733
TID
338
338
Oak Ridge National Laboratory Reports
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167
UC (Series)
155
155
ORNL (Series)
142
142
North American Aviation Reports
128
128
Report (U.S. Atomic Energy Commission)
126
126
Union Carbide Corporation Reports
110
110
U.S. Atomic Energy Commission Idaho Operations Office Reports
84
84
HW (Series)
70
70
General Electric Company Atomic Power Reports
34
34
Argonne National Laboratory Reports
33
33
Health and Safety Laboratory Reports
27
27
ANL (Series)
24
24
Battelle Memorial Institute Reports
23
23
Hanford Works Reports
23
23
Fallout Program Quarterly Summary Report
22
22
Oak Ridge Y-12 Plant Reports
21
21
University of California Radiation Laboratory Reports
18
18
IDO
17
17
BMI (Series)
14
14
Nuclear Superheat Quarterly Project Report
14
14
BNWL (Series)
13
13
Gas-Cooled Reactor Project Progress Report
13
13
Smoothed Thermocouple Tables of Extended Significance (°C)
12
12
Army Gas-Cooled Reactor Systems Program Progress Report
11
11
Lovelace Foundation Reports
9
9
Report (Battelle Memorial Institute. Columbus Laboratories)
9
9
Molten-Salt Reactor Program Semiannual Progress Report
7
7
Nuclear Development Corporation of America Reports
7
7
Pacific Northwest Laboratory Monthly Activities Report
7
7
APAE (Series)
6
6
General Electric Atomic Power Reports
6
6
Homogeneous Reactor Project Quarterly Progress Report
6
6
Piqua Nuclear Power Facility Operations Analysis Program Progress Report
6
6
United States Geological Survey Reports
6
6
AEC Unclassified Programs Progress Report
5
5
Analytical Chemistry Division Annual Progress Report
5
5
Knolls Atomic Power Laboratory Reports
5
5
Reactor Development Program Progress Report
5
5
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications
4
4
Babcock & Wilcox Company Reports
4
4
Combustion Engineering, Inc. Reports
4
4
Fast Ceramic Reactor Development Program Quarterly Report
4
4
Fiscal Year 1966
4
4
Molten-Salt Reactor Program Quarterly Progress Report
4
4
Reactor Technology Reports
4
4
Research report (Sandia Corporation)
4
4
Sandia Corporation Reports
4
4
Atomic Energy Commission Report
3
3
Civil Effects Test Operations Reports
3
3
E.I. du Pont de Nemours & Company Reports
3
3
EVESR Nuclear Superheat Fuel Development Project Quarterly Report
3
3
Feed Materials Production Center Summary Technical Report
3
3
Fiscal Year 1962
3
3
Gamma-Ray Spectrometry of Neutron-Deficient Isotopes Annual Progress Report
3
3
Health Physics Division Annual Progress Report
3
3
Instrumentation and Controls Division Annual Progress Report
3
3
Maritime Reactor Project Annual Progress Report
3
3
Neutron Physics Division Annual Progress Report
3
3
Oak Ridge Analytical Chemistry Division Annual Progress Report
3
3
Oak Ridge National Laboratory Chemical Technology Division Annual Progress Report
3
3
Pacific Northwest Laboratory Reports
3
3
The Flora of Healthy Dogs
3
3
Trace elements memorandum report
3
3
ABWR Quarterly Progress Report
2
2
AEC Research and Development Report
2
2
Accurate Nuclear Fuel Burnup Analyses Quarterly Report
2
2
Aircraft Nuclear Propulsion Project Quarterly Progress Report
2
2
Brookhaven National Laboratory Reports
2
2
CCCO (Series) (Philadelphia, Pennsylvania)
2
2
Catalytic Construction Company Reports
2
2
Chemical Technology Division Annual Progress Report
2
2
Fiscal Year 1961
2
2
Fiscal Year 1964
2
2
Fiscal Year 1965
2
2
Fiscal Year 1968
2
2
Fuel Cycle Program Progress Report
2
2
GEAP (Series)
2
2
Hallam Nuclear Power Facility Reactor Operations Analysis Program Semiannual Progress Report
2
2
Hanford Atomic Products Operation Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience
2
2
Hanford Radiological Sciences Research and Development Annual Report
2
2
In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes
2
2
Instrumentation and Controls Division Semiannual Progress Report
2
2
Metallurgy Division Annual Progress Report
2
2
NP (U.S. Atomic Energy Commission)
2
2
Oak Ridge Metals and Ceramics Division Annual Progress Report
2
2
Oak Ridge National Laboratory Nuclear Safety Program Progress Report
2
2
Organic Moderated Reactor Experiment Progress Report
2
2
Physics Division Annual Progress Report
2
2
Physics Division Semiannual Progress Report
2
2
Thermonuclear Project Semiannual Report
2
2
Trace elements investigations report
2
2
ANL Metallurgy Division Annual Report
1
1
Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report
1
1
Analog Simulation of the Hanford N-Reactor Plant
1
1
Annual Progress Report on Fuel Element Development
1
1
Applied Health Physics Annual Report
1
1
Applied Nuclear Physics Division Annual Progress Report
1
1
Argonne National Laboratory Annual Report
1
1
Army Reactors Program Annual Progress Report
1
1
Atomic Power Development Associates Reports
1
1
BNL (Series)
1
1
Chemistry Division Quarterly Progress Report
1
1
Electronic Devices for Nuclear Physics Quarterly Report
1
1
Electronuclear Research Division Annual Progress Report
1
1
Fast Ceramic Reactor Development Program Summary Report
1
1
Fast Flux Test Facility Studies Progress Report
1
1
Fiscal Year 1960
1
1
Fiscal Year 1963
1
1
Fission Product Inhalation Project
1
1
Fuels and Materials Development Program Quarterly Progress Report
1
1
Graphite Burnout Monitoring
1
1
KEWB Program Quarterly Progress Report
1
1
Liquid Metal Fuel Reactor Experiment Quarterly Technical Report
1
1
Low-Radioactivity-Level Waste Treatment
1
1
MTR Technical Branch Quarterly Report
1
1
MTR-ETR Technical Branches Quarterly Report
1
1
Mallinckrodt Chemical Works Reports
1
1
Metallurgy Division Quarterly Progress Report
1
1
Molten-Salt Reactor Program Progress Report
1
1
Nuclear Reactor Project Progress Report
1
1
ORNL Instrumentation and Controls Division Annual Progress Report
1
1
ORNL Instrumentation and Controls Division Progress Report
1
1
Oak Ridge Chemistry Division Annual Progress Report
1
1
Oak Ridge National Laboratory Instrumentation and Controls Division Annual Progress Report
1
1
Quarterly Progress Report Research and Development Activities Fixation of Radioactive Residues
1
1
Reactor Chemistry Division Annual Progress Report
1
1
Reactor Safety Quarterly Progress Report
1
1
Research and Development Activities in the Radiological Sciences
1
1
SL-1 Annual Operating Report
1
1
STEP Project Quarterly Technical Report
1
1
Snap-8 Corrosion Program Quarterly Progress Report
1
1
Solid State Division Annual Progress Report
1
1
Southwest Experimental Fast Oxide Reactor Development Program Quarterly Report
1
1
Texas Natural Resource Conservation Commission Reports
1
1
Thermonuclear Project Semiannual Progress Report
1
1
Two-Phase Pressure Losses Quarterly Progress Report
1
1
USAEC Idaho Operations Office Health and Safety Division Annual Report
1
1
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