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Subcooled burnout at high flows
Task II-B of the High Performance UO2 Program calls for testing a series of UO2 fuel rods in the PW loop of the GETR. The purpose of the tests is to obtain a relationship between the extent of central melting and the length of time before the fuel rod fails as a result of interaction between the fuel and the cladding.
Date:
unknown
Creator:
Janssen, E. (Engineer) & Kervinen, J. A.
System:
The UNT Digital Library
Design and Operating Experience of the ESADA Vallecitos Experimental Superheat Reactor (EVESR)
Summary: "The various design features significant to superheat are described for the 12-1/2 MW., 960 psig, 1050° F, steam-cooled, low-enriched, annular-fueled, experimental superheat reactor built by the General Electric Company at the Vallecitos Atomic Power Laboratory. Results obtained during the first six months of full-power operation, on the emergency cooling system, core thermal performance, and pressure vessel temperatures are presented and compared with predictions. Operating experience with over-all reactor system is also discussed."
Date:
February 1965
Creator:
Ianni, P. W.; Fritz, J. R. & Law, D. D.
System:
The UNT Digital Library
Pressure Vessel Steel Surveillance Program for General Electric Power Reactors
Abstract: "Pressure vessel steel surveillance programs are performed in nuclear power reactors to provide knowledge of the mechanical properties of the pressure vessel material as neutron irradiation proceeds. A standard surveillance program is described. Design of specimens, capsules, and associated equipment, as well as selection of test material and techniques for special preparation and testing, are discussed."
Date:
January 8, 1965
Creator:
Brandt, F. A.
System:
The UNT Digital Library
High Performance UO2 Program Quarterly Progress Report No. 12 January-March 1964
Work performed during the quarter is summarized by: direct measurement of fission gas pressure, loop operations, performance of UO2 fuel, UO2 grain growth and melting studies.
Date:
April 15, 1964
Creator:
Weidenbaum, B.
System:
The UNT Digital Library
High Performance UO2 Program Quarterly Progress Report No. 11 October-December 1963
Work performed during the quarter is summarized by: direct measurement of fission gas pressure, loop operations, performance of UO2 fuel, UO2 grain growth and melting studies.
Date:
January 15, 1964
Creator:
Weidenbaum, B.
System:
The UNT Digital Library
Consumers Big Rock Point Nuclear Power Reactor Stability Analysis
This report presents the results of an analysis which was undertaken to investigate the power stability of the Consumers Big Rock Point Nuclear Power Reactor.
Date:
1964?
Creator:
Case, J. M. & Holland, L. K.
System:
The UNT Digital Library
High Performance UO2 Program Quarterly Progress Report No. 13 April-June 1964
Work performed during the quarter is summarized by: loop operations, performance of UO2 fuel, UO2 grain growth and melting studies, fuel rod mechanism failure studies.
Date:
1964
Creator:
Weidenbaum, B.
System:
The UNT Digital Library
High Performance UO2 Program Quarterly Progress Report No. 10 July-September 1963
Work performed during the quarter is summarized by; direct measurement of fission gas pressure, loop operations, performance of UO2 fuel, UO2 grain growth and melting studies.
Date:
October 15, 1963
Creator:
Weidenbaum, B.
System:
The UNT Digital Library
High Performance UO2 Program Quarterly Progress Report No. 9 April-June 1963
Work performed during the quarter is summarized by: direct measurement of fission gas pressure, loop operations, performance of UO2 fuel, UO2 grain growth and melting studies.
Date:
July 15, 1963
Creator:
Weidenbaum, B.
System:
The UNT Digital Library
Burnout Conditions for Nonuniformly Heated Rod in Annular Geometry, Water at 1000 PSIA
Tests were run at the General Electric Company, Atomic Power Equipment Department, to determine the burnout conditions for a non-uniformly heated rod in an annular geometry.
Date:
June 1963
Creator:
Janssen, E. (Engineer) & Kervinen, J. A.
System:
The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Fifteenth Quarter, January-March 1963
From introduction: "This is the fifteenth in a series of quarterly reports which cover the progress and results from the conceptual designs, economic evaluations and research and development work performed by the General Electric Company as part of Contract AT(01-3)-189, Project Agreement No. 13."
Date:
May 15, 1963
Creator:
Flock, W. L.
System:
The UNT Digital Library
Physics Calculations for the Consumers Big Rock Point Process Computer
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.
System:
The UNT Digital Library
High Performance UO2 Program Quarterly Progress Report No.8 : January-March 1963
Work performed during the quarter is summarized by direct measurement of fission gas pressure, loop operations, performance of UO2 fuel.
Date:
April 15, 1963
Creator:
Weidenbaum, B.
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
High Performance UO2 Program Quarterly Progress Report No.7 : October-December 1962
Work performed during the quarter is summarized by direct measurement of fission gas pressure, loop operations, performance of UO2 fuel.
Date:
January 15, 1963
Creator:
Weidenbaum, B.
System:
The UNT Digital Library
Design Report: Superheat Strain - Cycle Capsule
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.
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
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
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
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
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
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
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
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