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Two-Phase Pressure Losses Third Quarterly Progress Report August 12-November 12, 1962
This is the third quarterly report on the work done under Contract AT(04-30-189, Project Agreement No.27, and covers the period August 12 to November 12, 1962.
Date:
December 12, 1962
Creator:
Janssen, E. (Engineer) & Kervinen, J. A.
System:
The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses: Fourth Quarterly Progress Report September-November, 1962
Work has continued on the development of accurate nuclear fuel burnup analysis. Work performed during the fourth quarter is summarized here.
Date:
December 1, 1962
Creator:
Rider, B. F.; Ruiz, C. P. & Peterson, J. P.
System:
The UNT Digital Library
The Measurement Of Free Fission Gas Pressure In Operating Reactor Fuel Elements
The experimental program described has had as its objective the determination of the pressure exerted by free fission gas in operating UO2-filled reactor fuel elements.
Date:
January 23, 1963
Creator:
Reynolds, M. B.
System:
The UNT Digital Library
Fabrication of Zirconium Alloys For Specific Zirconium Alloy Design Program
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.
System:
The UNT Digital Library
Heavy Element Isotopic Analysis of UO2 Fuel Irradiated In The VBWR: Report #1
The primary objective of this program is to obtain improved data on the changes in nuclear characteristics with burnup of uranium oxide fuel in a boiling water reactor.
Date:
December 28, 1962
Creator:
Hackney, M. R. & Ruiz, C. P.
System:
The UNT Digital Library
High Power Density Development Project Tenth Quarterly Progress Report July-September 1962
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.
System:
The UNT Digital Library
FORE - A Computational Program For The Analysis Of Fast Reactor Excursions
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.
System:
The UNT Digital Library
Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Ninth Quarterly Progress Report July 1962 - September 1962
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.
System:
The UNT Digital Library
Studies ot UO2-Cladding Mechanical Interactions (Short Time Irradiations in the GETR Trail Cable Facility)
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 evaluated.
Date:
October 1962
Creator:
Hazel, V. E.; Lyons, M. F. & Comprelli, F. A.
System:
The UNT Digital Library
Two-Phase Pressure Losses Second Quarterly Progress Report May 12-August 12, 1962
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.
System:
The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses: Third Quarterly Progress Report June - August, 1962
Work has continued on the development of accurate nuclear fuel burnup analysis. Work performed by the third quarter of 1962 is summarized.
Date:
October 1, 1962
Creator:
Rider, B. F.
System:
The UNT Digital Library
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
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.
System:
The UNT Digital Library
Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report April 1, 1962 - July 31, 1962
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.
System:
The UNT Digital Library
Power Cycling of High Power Density Fuel Specimens Clad With 10-Mil Wall Stainless Steel
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.
System:
The UNT Digital Library
Summary Safeguards Report For The Critical Experiment Facility Vallecitos Atomic Laboratory
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 Facility is also attached.
Date:
July 1962
Creator:
General Electric Company
System:
The UNT Digital Library
Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Quarterly Report For Period April 1 - June 30, 1962
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.
System:
The UNT Digital Library
High Power Density Development Project Ninth Quarterly Progress Report April-June 1962
Progress is reported on several tasks related to nuclear fuel development at the Consumers Power Company Big Rock Point Plant.
Date:
1962
Creator:
Holladay, R. L.
System:
The UNT Digital Library
Fuel Cycle Program, A Boiling Water Reactor Research and Development Program Eighth Quarterly Progress Report April 1962 - June 1962
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.
System:
The UNT Digital Library
Economic Evaluation of Control Rod Materials and Fabrication Processes
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.
System:
The UNT Digital Library
The Half-Life and Gamma Ray Abundance of Cs-137
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 method.
Date:
June 2, 1962
Creator:
Rider, B. F.; Peterson, J. P. & Ruiz, C. P.
System:
The UNT Digital Library
Sodium Mass Transfer: III - The Application of Liquid Ammonia as a Sodium Leaching Agent
A technique is presented for liquid ammonia leaching of metallic sodium from corrosion coupons, filter elements, and sodium samples to reveal contaminants and impurities.
Date:
April 1962
Creator:
Alter, H. W. & McManus, P. A.
System:
The UNT Digital Library
High Power Density Development Project Seventh Quarterly Progress Report October - December 1961
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.
System:
The UNT Digital Library
Sodium-Cooled Reactors Program: Fast Ceramic Reactor Development Program - Second Quarterly Report, January - March 1962
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.
System:
The UNT Digital Library
Sodium Cooled Reactors Program: Fast Ceramic Reactor Development Program Third Quarterly Report, April - June 1962
This is the third in a series of quarterly progress reports on the Fast Ceramic Reactor Program, an 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.
System:
The UNT Digital Library