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Numerical Computation of Neutron Distribution and Critical Size

Description: Report presenting a numerical calculation, by diffusion theory, of the critical size of a nuclear reactor, and of the time dependent distribution of neutrons in the reactor as a function of position (one-dimensional space) and neutron energy. The mathematical development of the numerical method, properties of the equations, and procedure are discussed in the report, along with a numerical example.
Date: February 15, 1950
Creator: Thompson, A. Stanley
Partner: UNT Libraries Government Documents Department
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Strain Fatigue Behavior of Zircaloy 2 and 3 at Room Temperature and 550°F

Description: Report describing a study performing strain-fatigue tests performed at room temperature and 550 degrees Fahrenheit on 1/2-inch hot-rolled and annealed plate of Zircaloy 2 and 3. The data is to be used on a S3G unit cell fuel element assembly. The report describes material and test procedure, a presentation of the results, and discussion of the results.
Date: November 18, 1957
Creator: Mehan, R. L.; Groleau, D. T.; Reed, J. H. & Sokol, G. J.
Partner: UNT Libraries Government Documents Department
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Brazing of Zircaloy 3 for Temperature Instrumented Probes

Description: Report describing a study to investigate the strength, ductility and corrosion resistance in 680 degree Fahrenheit water of several alloys for brazing Zircaloy 3 to itself. The conclusions and results of the study are summarized and data from the is presented in tables and summarized in the narrative.
Date: May 1, 1957
Creator: Gerken, J. M.
Partner: UNT Libraries Government Documents Department
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Evaluation of Seal Weld Joint Designs

Description: Report discussing a program to investigate the properties of two types of seal welds for Synthetic Aperture Radar (SAR) components. The objective of the study is to determine mechanical properties of concave canopy seal welds and convex canopy seal welds, determine if these two seal weld joint designs can be used safely for fabrication of SAR components, and to develop optimum welding conditions and weld joint designs for uniform full weld penetration using a concave and a convex canopy weld. T… more
Date: January 17, 1957
Creator: Kittle, D. B.
Partner: UNT Libraries Government Documents Department
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Evaluation of the Effects of Atomic Bomb Detonations in the State of Nevada on Air-Borne Contamination at Knolls Atomic Power Laboratory, Knolls Site and Environs

Description: Report investigating contamination of the atmosphere with radioactive elements above the normally expected levels at Knolls Atomic Power Laboratory (KAPL) - Knolls, Scandaga, and West Milton Sites - soon after the first atomic bomb was exploded in the Nevada testing station on January 27, 1951. Results are presented in graphs and in a narrative summary.
Date: May 7, 1951
Creator: Cherubin, L. J.
Partner: UNT Libraries Government Documents Department
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[Knolls Atomic Power Laboratory] Progress Report No. 14, September 1-30, 1947

Description: Monthly progress report discussing studies performed during September 1947 at the Knolls Atomic Power Laboratory, including the Hanford Research group, mechanical and optical devises, pile theory, nuclear physics, nuclear chemistry, separation chemistry, metallurgy, pile technology, and health studies.
Date: November 14, 1947
Creator: Knolls Atomic Power Laboratory.
Partner: UNT Libraries Government Documents Department
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DARTAB: A Program to Combine Airborne Radionuclide Environmental Exposure Data With Dosimetric and Health Effects Data to Generate Tabulations of Predicted Health Impacts

Description: Report describing the DARTAB computer code, which combines radionuclide environmental exposure data with dosimetric and health effects data to generate tabulations of the predicted impact of radioactive airborne effluents. The methodology and program specifications are discussed in the report.
Date: August 1981
Creator: Begovich, C. L.; Eckerman, K. F.; Schlatter, E. C.; Ohr, S. Y. & Chester, R. O.
Partner: UNT Libraries Government Documents Department
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Inhibitors to Transfer of Radioactive Stainless Steel Constituents in Sodium

Description: Report presenting a study on the inhibition of mass transfer of radioactive stainless steel components in a sodium system. The most effective element is identified. The design of the study is also discussed in the report and the results are presented in narrative form and tables.
Date: August 24, 1955
Creator: Mausteller, J. W. & Rodgers, S. J.
Partner: UNT Libraries Government Documents Department
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Feasibility of Establishing a National Burial Ground for Radioactive Waste in the Northeastern United States

Description: Report summarizing work investigating, interviewing, and making detailed studies of an area of the northeastern United States, within a 125-mile radius of Erie, Pennsylvania, to discover a possible site for a national land burial ground to receive and bury low and intermediate level radioactively contaminated waste. Estimated unit burial costs and computer transportation charges for a centrally located site are considered along with the quantity of waste anticipated, land burial requirements. P… more
Date: July 15, 1956
Creator: Morgan, James M., Jr. & Renn, Charles E.
Partner: UNT Libraries Government Documents Department
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Reservoir Evaluation Tests on RRGE 1 and RRGE 2, Raft River Geothermal Project, Idaho

Description: Report presenting the results of the production and interference tests conducted on the geothermal wells RRGE 1 and RRGE 2 in Raft River Valley, Idaho during September--November, 1975.. In all, three tests were conducted, two of them being short-duration production tests and one, a long duration interference test. In addition to providing estimates on the permeability and storage parameters of the geothermal reservoir, the tests also indicated the possible existence of barrier boundaries. Geomo… more
Date: May 1977
Creator: Narasimhan, Thiruppudaimarudhur N. & Witherspoon, Paul Adams
Location: See Bounding Coordinates
Partner: UNT Libraries Government Documents Department
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Compatibility of Materials in Liquid Metal

Description: Report describing a series of boundary laboratory tests conducted in liquid metal initiated to determine the materials which are best suited for use as sodium- or NaK-lubricated bearings under conditions of boundary lubrication. Results are presented in graphical and narrative form along with a discussion of the testing procedure, equipment, materials, and heat treatment specifications.
Date: August 18, 1951
Creator: Vail, Donald B.
Partner: UNT Libraries Government Documents Department
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Book No. 6: Laboratories Manual

Description: Report providing manual for nuclear reactors in the Pile Complex associated with, but not directly involved in, the pile operation: Pile Building, the Pile Laboratories, the Hot Laboratory, and the Waster System. The design, maintenance, and operation of these units are all covered, along with brief descriptions of structures and equipment, design methods and considerations
Date: July 1949
Creator: H.K. Ferguson Company
Partner: UNT Libraries Government Documents Department
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Feasibility Study of Boiling Water Reactor Nuclear Steam Supply Systems With Capacities Up to 10,000 MWt: Final Report

Description: Report describing a feasibility study of boiling water reactor (BWR) nuclear steam supply (NSS) systems with capacities up to 10,000 MWt. The results of the Oak Ridge Boiling Water Reactor feasibility study are presented. Included in the report are discussions of study objectives, conclusions and recommendations, core rating extrapolation, size limitations of essential BWR equipment items, feasibility study of large pressure vessels, conceptual designs of 5000 and 10,000 MWt NSS systems, and pl… more
Date: February 1967
Creator: Lockhart, R. W.
Partner: UNT Libraries Government Documents Department
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Development of a Thermionic Reactor Space Power System: Summary Report for Period, November 1, 1971 - February 29, 1972

Description: Report summarizing progress made on the development of a thermionic reactor space power system summarizing accomplishments made during a four-month period in materials technology, thermionic fuel element development, reactor technology, reactor experiment, and system technology.
Date: July 31, 1972
Creator: Gulf General Atomic Incorporated
Partner: UNT Libraries Government Documents Department
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Boiling Nuclear Superheater (BONUS) Power Station: Startup Summary Report

Description: Report discussing startup operations for the Boiling Nuclear Superheater (BONUS) Power Station at Rincón, Puerto Rico. Discussed are the nuclear and thermal characteristics of the integral boiling superheater core, the performance of the reactor auxiliary and emergency systems, the performance of the generating portion of the plant, the diverse problems that had to be resolved for the various systems and controls during the startup period, and the relatively minor problems which still exist. (I… more
Date: February 1966
Creator: Combustion Engineering, inc.
Partner: UNT Libraries Government Documents Department
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A Comparison of the Nuclear Defense Capabilities of Nuclear and Coal-Fired Power Plants

Description: Report comparing civil defense capabilities of 300-MWe nuclear and coal-fired power generation stations. The report evaluates the economics and feasibility of plant protection from nuclear attack by plant hardening, remote sitting, and utilizing option fueling options for coal-fired plants. (pg. 1)
Date: May 1962
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department
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Aerial Radiological Measuring Surveys of the Dresden Nuclear Power Station, July 1970

Description: Report discussing the Aerial Radiological Measuring System (ARMS) used to perform an aerial radiological survey of the Dresden Nuclear Power Station and surrounding area during July 1970. The survey included terrestrial background gamma radiation and a plume track of the stack release gases. A high-sensitivity detection system collected gamma spectral and gross-count data. The data were then computer processed into a isoexposure contour map, 3 ft above ground, of a 200 square mile area and a pl… more
Date: January 1973
Creator: EG & G, Inc. Las Vegas Area Operations
Location: See Bounding Coordinates
Partner: UNT Libraries Government Documents Department
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Aerial Radiological Measuring Survey of the Area Surrounding the Monticello Nuclear Generating Plant, Monticello, Minnesota, August 1970

Description: Report describing the Aerial Radiological Measuring System (ARMS) used to survey the Monticello Nuclear Generating Plant, Monticello and surrounding area during August 1970. The survey measured terrestrial background gamma radiation. A high-sensitivity detection system collected gamma spectral and gross-count data. The data were then computer processed into a map of a 625 square mile area showing isoexposure contours three feet above ground. (Abstract)
Date: September 1973
Creator: EG & G, Inc. Las Vegas Area Operations
Location: See Bounding Coordinates
Partner: UNT Libraries Government Documents Department
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Aerial Radiological Measuring Survey of the Area Surrounding the Enrico Fermi Atomic Power Plant, Monroe, Michigan, September 1970

Description: Report describing the Aerial Radiological Measuring System (ARMS) used to survey the Enrico Fermi Atomic Power Plant and surrounding area during September 1970. The survey measured terrestrial background gamma radiation and included a plume track of the stack release gases. A high-sensitivity detection system collected gamma spectral and gross-count data. The data were then computer processed into a map of a 277 sq. mile area showing isoexposure contours 3 ft above ground. (Abstract)
Date: September 1973
Creator: EG & G, Inc. Las Vegas Area Operations
Location: See Bounding Coordinates
Partner: UNT Libraries Government Documents Department
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1000-MWe Liquid Metal Fast Breeder Reactor (LMFBR) Follow-on Study: Tasks II & III, Westinghouse Conceptual Design Report

Description: Report presenting work performed by the Westinghouse Electric Corporation in fulfillment of their participation in the Atomic Energy Commission's 1000-MWe liquid metal fast breeder reactor (LMFBR) follow-on studies. This volume describes the conceptual design of a nuclear steam supply and energy conversion system including reactor design, fuel element fabrication and assembly, mechanical design of vessel internals, thermal and hydraulic design of the core, fuel management system, reactivity con… more
Date: April 1969
Creator: Westinghouse Electric Corporation. Advanced Reactors Division
Partner: UNT Libraries Government Documents Department
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1000-MWe Liquid Metal Fast Breeder Reactor Follow-on Study: Conceptual Design Report, Volume 5 - Methods

Description: Report discussing Atomics International's design studies for the 1000-MWe Liquid Metal Fast Breeder Reactor (LMFBR) Follow-on Program concerning Task III of these studies. Task III work includes a safety evaluation, core and system parametric study, and alternate plant and equipment configuration studies. The Task III final reference design is described in this report. This volume specifically describes methods of analysis and computer codes used in the study.
Date: 1969
Creator: North American Rockwell Corporation. Atomics International Division
Partner: UNT Libraries Government Documents Department
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1000-MWe Liquid Metal Fast Breeder Reactor Follow-on Study: Conceptual Design Report, Volume 4 - Description of Plant Design

Description: Report discussing Atomics International's design studies for the 1000-MWe Liquid Metal Fast Breeder Reactor (LMFBR) Follow-on Program concerning Task III of these studies. Task III work includes a safety evaluation, core and system parametric study, and alternate plant and equipment configuration studies. The Task III final reference design is described in this report. This volume specifically describes the reference plant design, and presents the specific engineering analyses which have been p… more
Date: 1969
Creator: Aronstein, R. E.; Beimler, D. W.; Belluomini, J.; Berg, G. E.; Berger, S.; Boardman, T. J. et al.
Partner: UNT Libraries Government Documents Department
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1000-MWe Liquid Metal Fast Breeder Reactor Follow-on Study: Conceptual Design Report, Volume 3 - Plant Safety Analyses

Description: Report discussing Atomics International's design studies for the 1000-MWe Liquid Metal Fast Breeder Reactor (LMFBR) Follow-on Program concerning Task III of these studies. Task III work includes a safety evaluation, core and system parametric study, and alternate plant and equipment configuration studies. The Task III final reference design is described in this report. This volume specifically a safety analysis of a selected group of accidents applicable to the Atomics International Task I prel… more
Date: 1969
Creator: Harper, B. E. & Hart, R. S.
Partner: UNT Libraries Government Documents Department
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1000-MWe Liquid Metal Fast Breeder Reactor Follow-on Study: Conceptual Design Report, Volume 2 - Engineering Studies

Description: Report discussing Atomics International's design studies for the 1000-MWe Liquid Metal Fast Breeder Reactor (LMFBR) Follow-on Program concerning Task III of these studies. Task III work includes a safety evaluation, core and system parametric study, and alternate plant and equipment configuration studies. The Task III final reference design is described in this report. This volume specifically presents the engineering studies, and discusses the selection of the final reference design.
Date: 1969
Creator: Aronstein, R. E. & Casey, D. F.
Partner: UNT Libraries Government Documents Department
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