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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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Physics Calculations for the Consumers Big Rock Point Process Computer

Description: The physics calculations to be performed on the Consumers On-Line Process Computer are reported. As a result of these calculations, a three-dimensional power shape is simulated, a reactivity balance is approximated, and the neutron exposure of each third of fuel bundle and control rod are accumulated. The work was reported as a part of the Consumers Research and Development Program.
Date: May 1963
Creator: Barth, N. H.
Partner: UNT Libraries Government Documents Department
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Design Report: Superheat Strain - Cycle Capsule

Description: In order to investigate the low frequency strain cycle fatigue for tubular sheath geometries an apparatus was designed and fabricated for laboratory and reactor experiments. The design of this apparatus is described herein.
Date: January 1963
Creator: Marburger, L.L.; Haglund, E. A.; Hafer, D. E.; Liffengren, D. J. & Armour, S. F.
Partner: UNT Libraries Government Documents Department
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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.
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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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.
Partner: UNT Libraries Government Documents Department
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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.
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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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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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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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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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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Fabrication of Zirconium Alloys For Specific Zirconium Alloy Design Program

Description: The raw materials and fabrication procedures employed in preparing thirty two zirconium alloy compositions for evaluation as described in GEAP-3979 are reported. Considerations involved in the extension of reported laboratory procedures to larger scale production are discussed.
Date: December 5, 1962
Creator: Antony, K. C. & Jones, L. T.
Partner: UNT Libraries Government Documents Department
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