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Symbols for Instrument Flowsheets and Drawings : a Recommended System for Application to ORNL Instrument Work

Description: This report supersedes ORNL CF-57-2-1, which was an extension and revision of ORNL CF-54-6-72. Details concerning a recommended system of flow-plan symbols and drawing are given. The system is designed to identify the function of all major instrument components and to show schematically the operation of the instrument relative to the particular process. The system is used for identification and designation. The system is a modification of the Instrument Society of American Recommended Practice … more
Date: June 19, 1962
Creator: Adams, R. K.; Davis, D. G.; Hyland, R. G. & Lieberman, B.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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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
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
open access

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.
Item Type: Refine your search to only Report
open access

High Power Density Development Project Seventh Quarterly Progress Report October - December 1961

Description: During the seventh quarter the twenty-four high power density fuel assemblies were irradiated in the VBWR to an average of about 2572 MWD/T. Also during this period the instrumental assembly tasks were completed, and the award of the contract for the Scheduling Computer was made. A summary of progress by task is presented here.
Date: 1962
Creator: Holladay, R. L.
Item Type: Refine your search to only Report
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Sodium-Cooled Reactors Program: Fast Ceramic Reactor Development Program - Second Quarterly Report, January - March 1962

Description: This is the second in a series of quarterly progress reports on the Fast Ceramic Reactor Development Program, an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide.
Date: 1962
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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High Power Density Development Project Eighth Quarterly Progress Report January - March 1962

Description: During the eighth quarter the instrumented assemblies were removed from VBWR and examined for effects of the exposure to reactor conditions. Also during this period the Big Rock developmental fuel assembly design was completed and a topical report was issued. A summary of progress by task is presented here.
Date: April 1, 1962
Creator: Holladay, R. L.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
open access

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.
Item Type: Refine your search to only Report
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