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Physics Pre-Startup Report: Esada Vallecitos Experimental Superheat Reactor

Description: This report defines the scope of the initial core loading and critical testing program and indicates acceptable methods for the execution of the tests. Included in the report is a compilation of results and conclusions from physics calculations performed to guide the testing and startup of the ESADA-Vallecitos Experimental Superheat Reactor (EVESR).
Date: April 12, 1963
Creator: Gietzen, A. J.; Tillinghast, T. & Weiss, M. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Two-Phase Pressure Losses: Fourth Quarterly Progress Report November 12, 1962 - February 12, 1963

Description: This is the fourth quarterly report on the work done under Contract AT(04-3)-189. The results reported here have to do primarily with single-phase loss and two-phase pressure drop in the 1/4" x 1-3/4" rectangular channel in the flow up and flow horizontal orientations, and two-phase pressure loss across two contraction-expansion inserts in the 1/2" x 1-3/4" channel.
Date: March 1, 1963
Creator: Janssen, E. (Engineer) & Kervinen, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium Mass Transfer: V. 1962 Test Run Report

Description: The General Electric Company has performed extensive tests as part of the USAEC Program to investigate Sodium Mass Transfer effects utilizing three prospective steel construction materials for a sodium cooled reactor system. This volume is a compilation of the reports for the eleven test runs completed during calendar year 1962.
Date: June 1963
Creator: Lockhart, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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General And Stress Corrosion Of High Nickel Alloys In Simulated Superheat Reactor Environment

Description: It is the purpose of this report to summarize the results of the evaluation program carried out to-date on the high nickel alloys Inconel, Incoloy and Hastelloy-X in the out-of-pile superheat facilities as part of Task E of the Atomic Energy Commission sponsored Superheat Program.
Date: March 1963
Creator: Pearl, W. L. & Gaul, G. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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General And Stress Corrosion Of High Nickel Alloys In Simulated Superheat Reactor Environment

Description: It is the purpose of this report to summarize the results of the evaluation program carried out to-date on the high nickel alloys Inconel, Incoloy and Hastelloy-X in the out-of-pile superheat facilities as part of Task E of the Atomic Energy Commission sponsored Superheat Program.
Date: January 1963
Creator: Pearl, W. L. & Gaul, G. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development Program For Increased Output In The Garigliano Nuclear Reactor : Quarterly Progress Report No. 1 September-December, 1962

Description: Authorization from the U.S. Atomic Energy Commission has been received to begin Pressure Vessel Sample Irradiation and Data logging and Computer System of the Development Program for Increased Output in the Garigliano Nuclear Reactor. The work described herein was performed in the period of September 1 to December 31, 1962.
Date: January 2, 1963
Creator: Quinn, E. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors : Seventh Quarterly Report October 1-December 31, 1962

Description: The objective of this program is the experimental determination of basic physical data and employment of these data to establish and confirm a theoretical model for predicting the long-term changes in isotopic composition and reactivity in plutonium-enriched, light-water-moderated reactors.
Date: December 31, 1962
Creator: Roskin, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Tenth Quarterly Progress Report October-December 1962

Description: The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor and other facilities to improve the technological limits of boiling water reactors in several areas.
Date: January 14, 1963
Creator: Howard, C. L.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High Power Density Development Project Tenth Quarterly Progress Report July-September 1962

Description: The Big Rock Point Reactor of the Consumers Power Company went critical for the first time on September 27, 1962. Summarized here are objectives and accomplishments of the pre-operational period as well as an indication of work scope remaining.
Date: October 1, 1962
Creator: Holladay, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Ninth Quarterly Progress Report July 1962 - September 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.
Date: October 25, 1962
Creator: Howard, C. L.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report April 1, 1962 - July 31, 1962

Description: This report covers the S-I-5-B-M fuel irradiation in the GETR Maritime Loop during the final quarter of fiscal year 1962 plus the month of July 1962 to conclude the irradiation program. The data are summarized in Section II.
Date: August 17, 1962
Creator: Danielson, D. W.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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