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Consumers Big Rock Point Nuclear Power Reactor Stability Analysis

Description: 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.
Partner: UNT Libraries Government Documents Department
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Control Worth of B4C Rods

Description: 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.)
Partner: UNT Libraries Government Documents Department
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Experimental Fast Ceramic Reactor Design Status Report as of October 31, 1961

Description: 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.
Partner: UNT Libraries Government Documents Department
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Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report October 1, 1961 - December 31, 1961

Description: 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.
Partner: UNT Libraries Government Documents Department
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High Performance UO2 Program Quarterly Progress Report Number 2: July-September 1961

Description: 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.
Partner: UNT Libraries Government Documents Department
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High Performance UO2 Program Third Quarterly Progress Report: October-December 1961

Description: 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.
Partner: UNT Libraries Government Documents Department
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Maritime Loop Irrradiation Program - Savannah I Fuel Irradiation: Progress Report First and Second Quarters, July, 1960-January, 1961

Description: 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 applica… more
Date: February 13, 1961
Creator: Marburger, I. L.
Partner: UNT Libraries Government Documents Department
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Compilation of Techniques Used By Vallecitos Radioactive Materials Laboratory

Description: 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.
Partner: UNT Libraries Government Documents Department
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Large High Power Density Core - Interim Report I: Physics Description of Reference Design

Description: 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.
Partner: UNT Libraries Government Documents Department
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VARI-II

Description: 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.
Partner: UNT Libraries Government Documents Department
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In-Core Instrumentation Development Program Quarterly Progress Report June - September 1963

Description: Introduction: The objective of Project Agreement 22 is to determine the feasibility of covering the complete reactor neutron flux start range from 10(3) - 5 x 10(13) nv by using in-core chambers. The counting mode of operating will be used at low neutron fluxes and the root mean square voltage fluctuation mode will be used at high neutron flux levels. Experiments have been run utilizing various ion chambers, gases, gas pressures, voltage, and cables to measure sensitivities and range operating … more
Date: October 1963
Creator: DuBridge, R. A.
Partner: UNT Libraries Government Documents Department
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In-Core Instrumentation Development Program Quarterly Progress Report September - December 1963

Description: Introduction: The objective of Project Agreement 22 is to determine the feasibility of using in-core ion chambers to cover the complete reactor neutron flux startup range from 10(4) -5 - 10(13) nv using in-core ion chambers. The counting mode of operation will be used at low neutron flux levels and the RMS voltage fluctuation mode (Campbell Theorem) will be used at high neutron flux levels. The June-September Progress Report (GEAP-4386) shows how the RMS voltage mode can be used, discusses c… more
Date: January 1964
Creator: DuBridge, R. A.
Partner: UNT Libraries Government Documents Department
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