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203 Matching Results
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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
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
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
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
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
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
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
High Power Density Development Project Eleventh Quarterly Progress Report, October-December 1962
Report on progress - fuel development, design of fuel slow system, physics development, and test planning
Date:
January 1, 1963
Creator:
Holladay, R. L.
System:
The UNT Digital Library
Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Tenth Quarterly Progress Report October-December 1962
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.
System:
The UNT Digital Library
Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors : Seventh Quarterly Report October 1-December 31, 1962
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.
System:
The UNT Digital Library