Nuclear Criticality Control in the EBR-II Fuel Cycle Facility

Nuclear Criticality Control in the EBR-II Fuel Cycle Facility
Author: J. C. Hesson
Publisher:
Total Pages: 40
Release: 1964
Genre: Breeder reactors
ISBN:


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An investigation has been made of criticality problems which might be encountered in EBR-II Fuel Cycle Facility. The purpose of the investigation was to determine quantity and configuration limits of the investigation was to determine quantity and configuration limits for EBR-II fuel of the first core composition during storage, handling and processing of this fuel material in the EBR-II Fuel Cycle Facility. Brief consideration in processing future EBR-II cores which are expected to contain plutonium as a fissionable matrial.


Nuclear Criticality Control in the EBR-II Fuel Cycle Facility
Language: en
Pages: 40
Authors: J. C. Hesson
Categories: Breeder reactors
Type: BOOK - Published: 1964 - Publisher:

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An investigation has been made of criticality problems which might be encountered in EBR-II Fuel Cycle Facility. The purpose of the investigation was to determi
Criticality Control Conditioning of Spent Nuclear Fuel in the Fuel Cycle Facility
Language: en
Pages:
Authors:
Categories:
Type: BOOK - Published: 1994 - Publisher:

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Transforming Criticality Control Methods for EBR-II Fuel Handling During Reactor Decommissioning
Language: en
Pages: 10
Authors:
Categories:
Type: BOOK - Published: 1995 - Publisher:

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A review of the Department of Energy (DOE) request to decommission the Experimental Breeder Reactor-II (EBR-II) was conducted in order to develop a scope of wor
Criticality Control During Conditioning of Spent Nuclear Fuel in the Fuel Cycle Facility
Language: en
Pages: 11
Authors: R. M. Lell
Categories:
Type: BOOK - Published: 1994 - Publisher:

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Nuclear Criticality Safety
Language: en
Pages: 256
Authors: Ronald Allen Knief
Categories: Technology & Engineering
Type: BOOK - Published: 1985 - Publisher: American Nuclear Society

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Nuclear criticality safety is the prevention of nuclear chain reactions in fissile materials outside of reactors. This book presents the underlying principles o