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FORE - A Computational Program For The Analysis Of Fast Reactor Excursions

Description: A digital computer program, FORE, which calculates transients for a fast reactor, has been coded for the TRANSAC 2000 computer. Its purpose is to provide understanding of the dynamics of fast reactors with particular emphasis on large ceramic-fueled fast reactors. The program calculates reactor power and temperatures of fuel, coolant, clad, and structure.
Date: October 16, 1962
Creator: Greebler, P.; Sherer, D. B. & Walton, N. H.
Partner: UNT Libraries Government Documents Department
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Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Program Summary and Sixth Quarterly Report, July 1 - September 30, 1962

Description: The work described in this report represents progress toward an agreement signed by the United States and the European Atomic Energy Community which provides a basis for cooperation in programs for the advancement of peaceful applications of atomic energy.
Date: October 15, 1962
Creator: Carver, J. G.; Lagache, M. P. & Morgan, W. R.
Partner: UNT Libraries Government Documents Department
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Power Cycling of High Power Density Fuel Specimens Clad With 10-Mil Wall Stainless Steel

Description: Three thin-wall stainless steel fuel specimens made using fabrication processes and materials similar to the Consumers Big Rock Plant research and development fuel rods were power cycled 3000 times between 500,000 and 75,000 BTU/hr-ft2 in the General Electric Test Reactor (GETR) Trail Cable facility. The fuel specimens were exposed to 1000 psi boiling water. All of the fuel specimens withstood the test without failing or without any significant changes in the clad characteristics.
Date: October 1962
Creator: Rowland, T. C. & Atkinson, J. S.
Partner: UNT Libraries Government Documents Department
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Studies ot UO2-Cladding Mechanical Interactions (Short Time Irradiations in the GETR Trail Cable Facility)

Description: This report is a supplement to GEAP-3759, Plastic Strain In Thin Fuel Element Cladding Due to UO2 Thermal Expansion. Cladding growth results are reported for repetitively irradiated, UO2 pellet-filled, annular capsules: for two UO2 powder-filled, annular capsules: and for six solid cylindrical pellet-filled capsules. Dimensional changes of the capsules irradiated during the entire program were analyzed, and the relationship of these results to the over-all fuel development program were evaluate… more
Date: October 1962
Creator: Hazel, V. E.; Lyons, M. F. & Comprelli, F. A.
Partner: UNT Libraries Government Documents Department
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Two-Phase Pressure Losses Second Quarterly Progress Report May 12-August 12, 1962

Description: This is the second quarterly report on the work done under Contract AT(04-3)-189, Project Agreement No. 27. The results reported here have to do primarily with the loss in a rectangular (1/2" x 1-3/4") channel in the horizontal orientation, without contraction-expansion inserts.
Date: September 12, 1962
Creator: Janssen, E. & Kervinen, J. A.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Eleventh Quarter, January-March 1962

Description: From introduction: "This is the eleventh of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: August 1962
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Quarterly Report For Period April 1 - June 30, 1962

Description: The Program fuel element has continued under irradiation in the Vallecitos Boiling Water Reactor, thermal energy group transfer cross sections for UO2 have been computed, and data have been reduced from the resonance wire activations performed last quarter. Future plans are included.
Date: July 15, 1962
Creator: Carver, J. G.; Morgan, W. R. & Robkin, M. A.
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Program, A Boiling Water Reactor Research and Development Program Eighth Quarterly Progress Report April 1962 - June 1962

Description: The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor (VBWR) and other facilities to improve the technological limits of boiling water reactors in several areas. This report presents updates on tasks related to those areas.
Date: July 10, 1962
Creator: Hodde, J. A.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Tenth Quarter, October-December 1962

Description: From introduction: "This is the tenth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: July 1962
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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Summary Safeguards Report For The Critical Experiment Facility Vallecitos Atomic Laboratory

Description: This report contains technical specifications and supporting data for the Critical Experiment Facility, information to justify operation of the facility, procedural control to be used to ensure safe operation, changes in neutron instrumentation and safety system, an evaluation of the safety of the Facility. It also contains descriptions of the site, the facility and the Critical Assemblies, operating standards and procedures. Amendment no.18 to license application for Critical Experiment Facili… more
Date: July 1962
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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Resonance Integral Calculations for Evaluation of Doppler Coefficients: The Rapture Code

Description: A code (RAPTURE) was programmed for the Philco TRANSAC 2000 computer to perform calculations needed for the evaluation of Doppler Coefficients in fast reactors with degraded neuron spectra. This code computes resonance integrals, averages them over resonance parameter distributions, and computes fission and capture cross sections as a function of fuel temperature and of potential scattering cross section per absorber isotope.
Date: June 12, 1962
Creator: Ferziger, Joel H.; Greebler, P.; Kelley, M. D. & Walton, J. W.
Partner: UNT Libraries Government Documents Department
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The Half-Life and Gamma Ray Abundance of Cs-137

Description: The nuclide Cs-137 is a fission product commonly used for measurement of uranium burnup in irradiated uranium fuel by the fission product to uranium ratio method. In the application of this method, the largest single error introduced in the measurement of burnup is the uncertainty in the half-life of Cs-137. Because of the uncertainty in this value and its importance in nuclear fuel burnup analysis, a reinvestigation was undertaken to obtain a more accurate value using the mass spectrometric me… more
Date: June 2, 1962
Creator: Rider, B. F.; Peterson, J. P. & Ruiz, C. P.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Ninth Quarter, July-September 1961

Description: From introduction: "This is the ninth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: June 1962
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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Application of Boron Carbide Nickel Dispersion to a Prototype Control Rod

Description: Previously reported results on the testing of small samples of boron carbide dispersed in nickel by electrolytic codeposition were adequately encouraging to lead to the development of a prototype control rod for operation in the Vallecitos Boiling Water Reactor. The operation of the control rod has been entirely satisfactory.
Date: May 1962
Creator: Williamson, H.E. & Alexander, A. J.
Partner: UNT Libraries Government Documents Department
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Economic Evaluation of Control Rod Materials and Fabrication Processes

Description: Control rod materials, designs, and fabrication processes are compared for their relative economies. Control rod lifetime data are calculated with a simple approximation of nuclear worth depreciation. These data are used in conjunction with the estimated fabrication costs to determine the cost of using several absorber materials in a typical power reactor on a cost-per-year basis. The effect the control system has on core power density and fuel lifetime is included.
Date: May 1962
Creator: Williamson, H. E. & Megerth, F. H.
Partner: UNT Libraries Government Documents Department
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Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report: January 1, 1962 -March 31, 1962

Description: This report covers the S-I-5-B-M fuel irradiation in the GETR Maritime Loop during the third quarter of fiscal year 1962. The data are summarized in Section II. Discussions on fuel performance, fuel environment (water chemistry), and loop operations are included.
Date: April 30, 1962
Creator: Danielson, D. W. & Gilbert, R. S.
Partner: UNT Libraries Government Documents Department
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Experimental Fast Ceramic Reactor Design Status Report as of October 31, 1961

Description: The design status of the Experimental Fast Ceramic Reactor (EFCR) is described for the period up to October 31, 1961. The primary purpose of the facility is to study the dynamic behavior of a fast ceramic reactor, including the experimental demonstration of the effectiveness of the Doppler coefficient in limiting the power excursion following a rapid insertion of reactivity.
Date: April 24, 1962
Creator: Horst, K. M.
Partner: UNT Libraries Government Documents Department
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