EBR-II Dry Critical Experiments

EBR-II Dry Critical Experiments PDF Author:
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 46

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Book Description
These experiments are preoperational zero-power nuclear investigations in the Experimental Breeder Reactor II (EBR-II) prior to insertion of sodium coolant. The experiments were performed with the power reactor instruments, fuel and mechanical components installed. The measured dry critical size, reactivity worth of control mechanisms and isothermal temperature coefficient of reactivity are in good agreement with predicted values. Additional measurements include neutron flux distributions in the uranium reflector and outside the reactor neutron shield.

EBR-II Dry Critical Experiments

EBR-II Dry Critical Experiments PDF Author:
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 46

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Book Description
These experiments are preoperational zero-power nuclear investigations in the Experimental Breeder Reactor II (EBR-II) prior to insertion of sodium coolant. The experiments were performed with the power reactor instruments, fuel and mechanical components installed. The measured dry critical size, reactivity worth of control mechanisms and isothermal temperature coefficient of reactivity are in good agreement with predicted values. Additional measurements include neutron flux distributions in the uranium reflector and outside the reactor neutron shield.

EBR-II Dry Critical Experiments

EBR-II Dry Critical Experiments PDF Author: L. J. Koch
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 92

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Book Description
Revisions in the reactor system and operating procedures necessary for carrying out a proposed dry critical experiment in the EBR-II are described. The safety aspect of the program is considered. The critical experiment will be conducted in the EBR-II prior to filling the primary system with sodium. The facility, experimental program, operational and experimental procedures, and hazards and plant safety are described.

EBR-II Wet Critical Experiments

EBR-II Wet Critical Experiments PDF Author: F. S. Kirn
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 50

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Book Description
The EBR-II Wet Critical Experiments were designed to provide two general, but not mutually exclusive, types of information. First there are the data that are essential for operating the power reactor system. These include control rod worth, neutron source strength, nuclear instrument response, etc. The second type of data is of more general interest, including the total worth of the sodium coolant, critical size, and the isothermal temperature coefficient of reactivity.

Addendum to Hazard Summary Report

Addendum to Hazard Summary Report PDF Author: L. J. Koch
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 334

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Book Description
The initial "Hazard Summary Report - Experimental Breeder Reactor-II (EBR-II)" was published as ANL-5719 in May, 1957. At the time of preparation of ANL-5719 (early 1957), the design of the EBR-II Facility was in progress - construction had not started. This Addendum is limited, for the most part, to changes which have been made in the EBR-II Facility, and to supporting experimental data developed, since the publication of ANL-5719.

EBR-II WET CRITICAL EXPERIMENTS.

EBR-II WET CRITICAL EXPERIMENTS. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Reactor Development Program Progress Report

Reactor Development Program Progress Report PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 70

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The Physics Design of the EBR-II

The Physics Design of the EBR-II PDF Author: W. B. Loewenstein
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 78

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Book Description
The physics design problems of the EBR-II are summarized. These include analysis of the EBR-II engineering design as well as applicable zero-power critical experiments. Pertinent reactor safety problems are reviewed. Safety considerations bearing on normal plant operation and manipulations within the reactor are emphasized. The implication of controlled in-pile meltdown experiments is considered. Irradiation damage and metallurgical phase phenomena are summarized and related to reactivity. The nuclear performance of the system is considered in terms of actual plant operation. The predicted shift of both power and reactivity from core to radial reflector is described.

Reactor Development Program Progress Report

Reactor Development Program Progress Report PDF Author: N. Hilberry
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 98

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Reactor Technology

Reactor Technology PDF Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 876

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TID.

TID. PDF Author:
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 720

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