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Light-Water-Reactor Safety Research Program

Description: Report of a long-term program for monitoring the irradiation behavior of the materials in service in the primary-system sodium and the neutron shield of the EBR-11 sodium-cooled fast breeder reactor.
Date: 1977?
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department
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Light-Water-Reactor Safety Research Program

Description: Progress report on water-reactor-safety heat-transfer and flow problems. Covering the following research and development areas: loss-of-coolant accident research, transient fuel response and fission-product release program, mechanical properties of zircaloy containing oxygen, and steam-expulsion studies.
Date: December 1976
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department
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Light-Water-Reactor Safety Research Program

Description: This progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1976 on water-reactor-safety heat-transfer and flow problems. The following research and development areas are covered: (1) Loss of coolant Accident Research: Heat Transfer and Fluid Dynamics; (2) Transient Fuel Response and Fission-product Release Program; (3) Mechanical Properties of Zircaloy Containing Oxygen; and (4) Steam-explosion Studies.
Date: 1976?
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department
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Light-Water-Reactor Safety Research Program Quarterly Progress Report: October-December 1976

Description: Quarterly progress report summarizing work performed by the Argonne National Laboratory Light-Water-Reactor Safety Research Program. It includes sections discussing research and development in: (1) loss of-coolant accident research: heat transfer and fluid dynamics; (2) transient fuel response and fission-product release program; (3) mechanical properties of zircaloy containing oxygen; and (4) steam-explosion studies.
Date: March 1977
Creator: Sachs, Robert G. & Kyger, Jack A.
Partner: UNT Libraries Government Documents Department
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Light-Water-Reactor Safety Research Program Quarterly Progress Report: July-September 1977

Description: Quarterly report summarizing research and development on water-reactor-safety heat-transfer and flow problems, including: Loss-of-coolant accident research, transient fuel response and fission-product release, mechanical properties of zircaloy containing oxygen, and steam-explosion studies.
Date: January 1978
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department
open access

Light-Water-Reactor Safety Research Program Quarterly Progress Report: January-March 1978

Description: Quarterly report summarizing research and development by Argonne National Laboratory on water-reactor-safety heat-transfer and flow problems, including: Loss-of-coolant Accident Research: Heat Transfer and Fluid Dynamics, Transient Fuel Response and Fission-product Release Program, Mechanical Properties of Zircaloy Containing Oxygen,and Steam-explosion Studies.
Date: 1978?
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department
open access

Light-Water-Reactor Safety Research Program, Quarterly Progress Report: October-December 1975

Description: Quarterly report summarizing work by Argonne National Laboratory on water-reactor-safety heat-transfer and flow problems. "The following research and development areas are covered: (1) Loss-of-coolant Accident Research: Heat Transfer and Fluid Dynamics; (2) Transient Fuel Response and Fission-product Release Program; and (3) Mechanical Properties of Zircaloy Containing Oxygen" (p. x).
Date: 1976?
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department
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