Nuclear Fuel Research Fuel Cycle Development Program Quarterly Progress Report July 1 to September 30, 1961 PDF Download

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1961 1961

Nuclear Fuel Research Fuel Cycle Development Program Quarterly Progress Report July 1 to September 30, 1961

Author: Olin Mathieson Chemical Corporation. Nuclear Fuel Research Laboratory
Publisher:
ISBN:
Category :
Languages : en
Pages : 20

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Book Description

Nuclear Fuel Research Fuel Cycle Development Program Quarterly Progress Report July 1 to September 30, 1961

Author: Olin Mathieson Chemical Corporation. Nuclear Fuel Research Laboratory
Publisher:
ISBN:
Category :
Languages : en
Pages : 20

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Book Description

Nuclear Fuel Research Fuel Cycle Development Program Quarterly Progress Report October 1 to December 31, 1960

Author: Olin Mathieson Chemical Corporation. Nuclear Fuel Research Laboratory
Publisher:
ISBN:
Category :
Languages : en
Pages : 26

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Nuclear Fuel Research Fuel Cycle Development Program Quarterly Progress Report January 1 to March 31, 1961

Author: Olin Mathieson Chemical Corporation. Nuclear Fuel Research Laboratory
Publisher:
ISBN:
Category :
Languages : en
Pages : 33

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Nuclear Fuel Research Fuel Cycle Development Program Quarterly Progress Report

Author:
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 36

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Nuclear Fuel Research Fuel Cycle Development Program Quarterly Progress Report April 1 to June 30, 1960

Author: Herbert S. Kalish
Publisher:
ISBN:
Category :
Languages : en
Pages : 22

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Nuclear Fuel Research Fuel Cycle Development Program Quarterly Progress Report

Author:
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 28

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Nuclear Fuel Research Fuel Cycle Development Program

Author: E. Gordon
Publisher:
ISBN:
Category : Metal crystals
Languages : en
Pages : 42

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NUCLEAR FUEL RESEARCH FUEL CYCLE DEVELOPMENT PROGRAM QUARTERLY PROGRESS REPORT, OCTOBER 1-DECEMBER 31, 1961

Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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The irradiation testing program involving enriched UO2 capsules fabricated by low-temperature sintering was continued. Flux monitor data indicate an average burnup level in the capsule of 5800 Mwd/t compared with 9100 Mwd/t calculated. Preparation of 5 different high-purity UC irradiation test specimens of 12% enrichment is reported. Bescriptions of UC preparation procedures by the propane reaction and by skull melting are included. (J.R.D.).

Proceedings of the Uranium Carbide Meeting

Author:
Publisher:
ISBN:
Category : Uranium
Languages : en
Pages : 172

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TID.

Author:
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 172

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