This system will be undergoing maintenance Tuesday, December 6 from 9AM to 12PM CST.

  You limited your search to:

  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: TID
 Collection: Technical Report Archive and Image Library
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. digital.library.unt.edu/ark:/67531/metadc783725/
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 a n estimation of the state of technology in 1980." digital.library.unt.edu/ark:/67531/metadc101110/
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." digital.library.unt.edu/ark:/67531/metadc101111/
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 3, Concept IV 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 II description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On-Study Program." digital.library.unt.edu/ark:/67531/metadc101112/
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 4, Concept III System Description
From introduction: "The third of four designs to be developed by Babcock & Wilcox (B&W), Concept III observes ground rules established under the LMFBR Follow-On Program and is based on the estimated state of technology in 1980." digital.library.unt.edu/ark:/67531/metadc101113/
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." digital.library.unt.edu/ark:/67531/metadc101114/
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. digital.library.unt.edu/ark:/67531/metadc100653/
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. digital.library.unt.edu/ark:/67531/metadc173360/
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." digital.library.unt.edu/ark:/67531/metadc100242/
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. digital.library.unt.edu/ark:/67531/metadc784241/
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. digital.library.unt.edu/ark:/67531/metadc784242/
Advanced Pressurized Water Reactor Study [Part 3]: 235 Mw Coal-fired Generating Plant
... digital.library.unt.edu/ark:/67531/metadc784243/
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." digital.library.unt.edu/ark:/67531/metadc67315/
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." digital.library.unt.edu/ark:/67531/metadc67316/
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." digital.library.unt.edu/ark:/67531/metadc67314/
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." digital.library.unt.edu/ark:/67531/metadc67313/
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. digital.library.unt.edu/ark:/67531/metadc783727/
Aerospace Nuclear Safety: October 1 - 4, 1963
Proceedings on aerospace nuclear safety. digital.library.unt.edu/ark:/67531/metadc303861/
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. digital.library.unt.edu/ark:/67531/metadc100255/
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. digital.library.unt.edu/ark:/67531/metadc100570/
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). digital.library.unt.edu/ark:/67531/metadc100630/
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). digital.library.unt.edu/ark:/67531/metadc100655/
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. digital.library.unt.edu/ark:/67531/metadc100650/
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. digital.library.unt.edu/ark:/67531/metadc101088/
Analytical Chemistry Division Annual Progress Report, December 31, 1960
Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division. digital.library.unt.edu/ark:/67531/metadc100439/
Analytical Chemistry Division Annual Progress Report for Period Ending November 15, 1964
Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Analytical Chemistry Division. Instrumentation, analytical methods, reactor projects, service analysis, and special research is presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100290/
Analytical Chemistry in Nuclear Reactor Technology: 1961
... digital.library.unt.edu/ark:/67531/metadc784220/
Annual Report for 1963: Metallurgy Division
Report issued by the Argonne National Laboratory discussing work conducted by the Metallurgy Division during 1963. Annual experiments, programs, and studies are presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc170918/
The Application of Data Processing Techniques to a Maintenance Work Control Program
Description of a data collection and reporting system which was devised and installed in the Union Carbide Nuclear Company's Y-12 Plant Maintenance Division. digital.library.unt.edu/ark:/67531/metadc173354/
Applied Health Physics Annual Report for 1963
Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100291/
Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956
Report issued by the Oak Ridge National Laboratory discussing work completed by the Applied Nuclear Physics Division during 1956. Summaries of experiments conducted and project developments are presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100292/
Argonne High-Flux Research Reactor: AHFR Conceptual Design Study
Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc67190/
Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959
Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1). digital.library.unt.edu/ark:/67531/metadc67293/
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1959
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation. digital.library.unt.edu/ark:/67531/metadc67298/
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1959
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation. digital.library.unt.edu/ark:/67531/metadc67299/
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation. digital.library.unt.edu/ark:/67531/metadc67300/
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1960
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation. digital.library.unt.edu/ark:/67531/metadc67301/
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961
Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations. digital.library.unt.edu/ark:/67531/metadc67302/
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation. digital.library.unt.edu/ark:/67531/metadc67303/
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1963
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation. digital.library.unt.edu/ark:/67531/metadc67294/
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1963
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation. digital.library.unt.edu/ark:/67531/metadc67295/
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1964
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation. digital.library.unt.edu/ark:/67531/metadc67296/
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1964
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation. digital.library.unt.edu/ark:/67531/metadc67297/
Army Reactors Program Annual Progress Report: 1962
Report summarizing ongoing nuclear work performed by the ORNL for the United States Army. digital.library.unt.edu/ark:/67531/metadc100409/
Atomic Energy Facts: a Summary of Atomic Activities of Interest to Industry
Introduction: Atomic Energy Facts is designed to serve as an introduction to nuclear operations in the United States and as a handbook of related information for the use of industrial firms and other active or interested in atomic energy. digital.library.unt.edu/ark:/67531/metadc783726/
Attenuation in Water of Radiation from the Bulk Shielding Reactor: Measurements of the Gamma-Ray Dose Rate, Fast Neutron Dose Rate, and Thermal-Neutron Flux
Report issued by the Oak Ridge National Laboratory displaying a single chart showing measurements of the gamma-ray, fast-neutron, and thermal-neutron dose rates. digital.library.unt.edu/ark:/67531/metadc100326/
An Automatic Analyzing Monitor for Reactor Effluent Cooling Water
From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water." digital.library.unt.edu/ark:/67531/metadc100577/
Automatic Mass Spectrometer for Isotopic Analysis of Lithium
Report discussing an improvement program on lithium mass spectrometers. digital.library.unt.edu/ark:/67531/metadc173352/
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. digital.library.unt.edu/ark:/67531/metadc100623/
Beta-Gamma Dose Rates from U232 in U233
This report defines in detail the source of the dose rate of U233 and describes a method by which they may be predicted. digital.library.unt.edu/ark:/67531/metadc100648/
FIRST PREV 1 2 3 4 5 NEXT LAST