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Experimental Study of the Neutronics of the First Gas Cooled Fast Reactor Benchmark Assembly (GCFR Phase 1 Assembly)

Description: The Gas Cooled Fast Reactor (GCFR) Phase I Assembly is the first in a series of ZPR-9 critical assemblies designed to provide a reference set of reactor physics measurements in support of the 300 MW(e) GCFR Demonstration Plant designed by General Atomic Company. The Phase I Assembly was the first complete mockup of a GCFR core ever built. A set of basic reactor physics measurements were performed in the assembly to characterize the neutronics of the assembly and assess the impact of the neutron… more
Date: December 1976
Creator: Bhattacharyya, S. K.
Partner: UNT Libraries Government Documents Department
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Summary and Evaluation of Fuel Dynamics Transient-Overpower Experiments : Status 1974

Description: The report summarizes and evaluates experiments conducted in the Transient Reactor Test Facility (TREAT) using the Mark-II loop facility. The tests discussed are of the E and H series. Detailed descriptions of test conditions and test results as of February 1974 are presented. Since all data have not been acquired on all experiments, this report must be considered interim in nature. Particular emphasis is placed on data relevant to Fast Test Reactor (FTR) safety-analysis efforts.
Date: June 1977
Creator: Deitrich, L. W.; Doerner, R. C.; Hughes, T. H. & Wright, A. E.
Partner: UNT Libraries Government Documents Department
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Neoprene and Nickel Linings : NYX Test No. 1.3.4

Description: Abstract: "Stainless steel valves, pumps, and heat exchangers were not available for NYX start-up. Cast iron and steel equipment was protected against corrosion by lining with neoprone and nickel plate. The linings failed under flow conditions and their use was discontinued. Chromate inhibitor was used to reduce rusting for the reminder of the test program."
Date: December 1952
Creator: Poss, Fred J. & Longtin, Bruce
Partner: UNT Libraries Government Documents Department
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Performance of the Disassembly Equipment : NYX Test No. 2.9.1, 2.9.3

Description: Abstract: "The NYX testing of the component disassembly equipment comprised repeated operation of both the quatrefoil disassembly machine and the foil press and shear to evaluate the suitability of these machines to perform their design function with reliability and convenience of operation. During testing, both design and operational deficiencies were found and corrected in the NYX equipment. In general, both machines operated satisfactorily after modification."
Date: February 1953
Creator: Bernath, Louis & Thompson, J. N., Jr.
Partner: UNT Libraries Government Documents Department
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Operational Physics Data from the HWCTR

Description: The Heavy Water Components Test Reactor (HWCTR) was built for the Atomic Energy Commission by the Du Pont Company to satisfy a need for fuel testing in the AEC's Heavy Water Power Reactor Program. The reactor was designed to provide a realistic test environment for full size fuel candidates. The report contains sections on (1) the containment building, (2) vertical cross section of the reactor vessel, (3) core layout, (4) low power physics tests and comparison with calculations, (5) rod worth… more
Date: September 20, 1963
Creator: Rusche, Benard Clements, 1931-
Partner: UNT Libraries Government Documents Department
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Facility For Photographing in-Pile Meltdown Experiments in TREAT

Description: Report regarding the fabrication of a transparent meltdown facility for the purpose of photographing simulated meltdowns.
Date: January 1962
Creator: Golden, G. H.; Dickerman, C. E. & Robinson, L. E.
Partner: UNT Libraries Government Documents Department
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Advanced Test Reactor Turbo Report

Description: From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."
Date: January 1964
Creator: Turner, Robert A.
Partner: UNT Libraries Government Documents Department
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Advanced Test Reactor Servo Regulator Rod Test Program

Description: From abstract: "Verify rod mechanism characteristics reported by the United Shoe Machinery Corporation, demonstrate that rod mechanism characteristics were compatible with reactor kinetics and that over-all reactor system behavior was stable, and to recommend system modifications needed for satisfactory performance."
Date: February 1964
Creator: Pickett, R. T., III
Partner: UNT Libraries Government Documents Department
open access

Advanced Test Reactor Burnout Heat Transfer Tests

Description: From abstract: "Results of burnout test to determine the limiting heat flux in a simulated Advanced Test Reactor fuel element channel."
Date: January 1964
Creator: Croft, M. W.
Partner: UNT Libraries Government Documents Department
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