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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
Control Worth of B4C Rods
This report considers the theoretical evaluation of a system for gaining increased control strength and increased control lifetime and presents a theoretical model which is applicable to conventional multigroup diffusion theory.
Date:
August 30, 1961
Creator:
Pomraning, G. C. (Gerald C.)
System:
The UNT Digital Library
Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report: April 1, 1961-June 30, 1961
This report covers the S-I-5-B-M* fuel irradiation in the GETR Maritime Loop during the fourth quarter of fiscal year 1961. The data are summarized in Section II.
Date:
August 25, 1961
Creator:
Danielson, D. W.
System:
The UNT Digital Library
Consumers Baffle Two-Phase Air-Water Flow Tests in a One-Fifth Scale Model
Tests in a one-fifth scale clear plastic model were conducted to investigate the flow characteristics of the asymmetrical riser configuration in the Consumers Big Rock power plant.
Date:
September 1961
Creator:
Swan, C. L.
System:
The UNT Digital Library
Fuel Cycle Program - A Boilng Water Reactor Research and Development Program. Fifth Quarterly Report, July 1961-September 1961
This report summarizes progress on investigation into improving the technological limits of boiling water reactors, Vallecitos Boiling Water Reactor and other facilities.
Date:
October 10, 1961
Creator:
Hodde, J. A.
System:
The UNT Digital Library
Program For the Development of Plutonium Recycle For Use in Light Water Moderated Reactors: Third Quarterly Report
This is a report of work completed during the period October 1, 1961, to December 31, 1961. The Program fuel element was completed and assembled. After extensive analysis, it was concluded that the fuel was satisfactory for use in the Program.
Date:
January 5, 1962
Creator:
Carver, J. G.
System:
The UNT Digital Library
Experimental Fast Ceramic Reactor Design Status Report as of October 31, 1961
The design status of the Experimental Fast Ceramic Reactor (EFCR) is described for the period up to October 31, 1961. The primary purpose of the facility is to study the dynamic behavior of a fast ceramic reactor, including the experimental demonstration of the effectiveness of the Doppler coefficient in limiting the power excursion following a rapid insertion of reactivity.
Date:
April 24, 1962
Creator:
Horst, K. M.
System:
The UNT Digital Library
Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report October 1, 1961 - December 31, 1961
This report covers the S-I-5-B-M fuel irradiation in the GETR Maritime Loop during the second quarter of fiscal year 1962. The data are summarized in Section II. Discussions on fuel performance, fuel environment (water chemistry), problems with loop operations, and the crud deposition program are included.
Date:
January 31, 1962
Creator:
Danielson, D. W. & Gilbert, R. S.
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
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
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.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
High Performance UO2 Program Quarterly Progress Report No. 6 : July-September 1962
Work performed during the quarter is summarized by direct measurement of fission gas pressure, loop operations, performance of UO2 fuel.
Date:
1962
Creator:
Weidenbaum, B.
System:
The UNT Digital Library
High Performance UO2 Program Quarterly Progress Report Number 2: July-September 1961
The primary purpose of this joint USAEC-Euratom program is to obtain a better understanding if the maximum achievable operating characteristics of UO2 as a reactor fuel. During the program work will be performed in two areas that have been of concern to reactor core designers for a long time, namely fission gas release and central melting in fuel rods.
Date:
October 1, 1961
Creator:
Weidenbaum, B.
System:
The UNT Digital Library
High Performance UO2 Program Third Quarterly Progress Report: October-December 1961
The primary purpose of this joint USAEC-Euratom program is to obtain a better understanding of the maximum achievable operating characteristics of UO2 as a reactor fuel. During the program work will be performed in two areas that have been of concern to reactor core designers for a long time, namely, fission gas release and central melting in fuel rods.
Date:
January 2, 1962
Creator:
Weidenbaum, B.
System:
The UNT Digital Library
High Performance UO2 Program Fourth Quarterly Progress Report
This phase of the program is concerned with irradiation of fuel assemblies to determine central temperature limitations.
Date:
April 1, 1962
Creator:
Weidenbaum, B.
System:
The UNT Digital Library
High Performance UO2 Program Quarterly Progress Report No.5: April-June 1962
Work performed during the quarter is summarized by direct measurement of fission gas pressure, loop modifications, UO2 fuel performance
Date:
June 1962
Creator:
Weidenbaum, B.
System:
The UNT Digital Library
Maritime Loop Irrradiation Program - Savannah I Fuel Irradiation: Progress Report First and Second Quarters, July, 1960-January, 1961
The General Electric Company is proceeding with an irradiation program to proof test a representative array of Savannah I fuel rods. Irradiation of a test assembly containing Savannah I fuel rods has begun and it is proposed that the results of this irradiation will permit an advance evaluation of the fuel performance and fuel burnup in the Savannah I reactor. This report covers the first two quarters of the reporting period. All aspects of the subject program have been consolidated and applicable portions are discussed in some detail.
Date:
February 13, 1961
Creator:
Marburger, I. L.
System:
The UNT Digital Library
Compilation of Techniques Used By Vallecitos Radioactive Materials Laboratory
Equipment and techniques for remote examination of irradiated fuel assemblies applicable to the Maritime Program are described. The following subjects are covered: visual and photographic examination, dimensional measurements, gamma activity scanning, fission gas release and fuel rod void volume determinations, density measurements, metallographic examination, and radiochemical burnup analysis.
Date:
February 1961
Creator:
Brandt, F. A.; Mathay, P. W. & Zimmerman, D. L.
System:
The UNT Digital Library
Large High Power Density Core - Interim Report I: Physics Description of Reference Design
A reference design of a large high power density core has been established representing the available technology as of August, 1960. Reference core performance and cost should improve considerably after incorporation of improvements now under study.
Date:
February 3, 1961
Creator:
Miller, C. L.
System:
The UNT Digital Library
Pressure Drop Along a Fuel Cycle Fuel Assembly - Various Orifice Configurations
The objective is to establish, from test results, the relationship between pressure loss and orifice configuration, mass rate, and steam quality, for a Fuel Cycle fuel assembly.
Date:
May 22, 1961
Creator:
Janssen, E. (Engineer) & Kervinen, J. A.
System:
The UNT Digital Library
VARI-II
Writing the VARI-II Program was motivated by the need for a method of analyzing the results for the Absorber Burn-Up Experiment in progress at the Vallecitos Atomic Laboratory.
Date:
March 10, 1961
Creator:
Russell, J. L. (John L.), Jr.
System:
The UNT Digital Library