Design and Analysis of Instrumented Subassembly System for EBR-II

Design and Analysis of Instrumented Subassembly System for EBR-II PDF Author: A. Smaardyk
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 50

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Instrumented Subassembly System and In-core Instrument Test Facility for EBR-II.

Instrumented Subassembly System and In-core Instrument Test Facility for EBR-II. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 32

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Book Description
EBR-II (Experimental Breeder Reactor No. 2) was originally designed and operated by ANL as a demonstration of a fast breeder central station reactor. After successful demonstration of this goal, including a "quick turn-around" fuel cycle, the reactor was converted into an irradiation test facility. Numerous types of irradiation sub-assemblies were designed and constructed. In addition, two types of experimental facilities will serve to provide instrument read-out data during the life of the experiments, while the reactor is operating. The two types are "The Instrumented Subassembly System", and "The In-Core Instrument Test Facility". The study shows that temperatures of 900°-1350°F could be attained during reactor operation. Temperatures above and below this range would cause heat transfer or stress problems. It is intended to make it possible to remove and insert individual tests without effecting the remaining instruments being tested.

Design and Analysis of Instrumented Subassembly System for EBR-II

Design and Analysis of Instrumented Subassembly System for EBR-II PDF Author: A. Smaardyk
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 50

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EBR-II Instrumented-subassembly System

EBR-II Instrumented-subassembly System PDF Author: W.M. Thompson
Publisher:
ISBN:
Category : Design
Languages : en
Pages : 143

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EBR-II Instrumented-subassembly System

EBR-II Instrumented-subassembly System PDF Author: W. M. Thompson
Publisher:
ISBN:
Category : Design
Languages : en
Pages : 0

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Conceptual System Design Description of the System for Emergency Removal of EBR-II Instrumented Subassemblies (INSER)

Conceptual System Design Description of the System for Emergency Removal of EBR-II Instrumented Subassemblies (INSER) PDF Author: Peter Elias
Publisher:
ISBN:
Category :
Languages : en
Pages : 39

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PNL-17 EBR-II Instrumented Subassembly Test

PNL-17 EBR-II Instrumented Subassembly Test PDF Author: M. K. Millhollen
Publisher:
ISBN:
Category : Thermocouples
Languages : en
Pages : 52

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EBR-II

EBR-II PDF Author:
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ISBN:
Category :
Languages : en
Pages :

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Experimental Breeder Reactor II (EBR-II) has been operating for nearly 20 years as part of the foundation of the US Department of Energy's LMFBR development program. During that time, the EBR-II fuel-handling system has performed extremely well, especially considering the conditions under which much of the system operates and the reliability required to maintain the high plant factor routinely demonstrated by EBR-II. Since EBR-II is a pool-type reactor, much of the fuel handling is done remotely within the sodium-filled primary tank at 371°C. Activities involved in locating a misplaced fuel subassembly in the primary tank are described.

CONCEPTUAL SYSTEM DESIGN DESCRIPTION OF THE SYSTEM FOR EMERGENCY REMOVAL OF EBR-II INSTRUMENTED SUBASSEMBLIES (INSER). EBR-II Project

CONCEPTUAL SYSTEM DESIGN DESCRIPTION OF THE SYSTEM FOR EMERGENCY REMOVAL OF EBR-II INSTRUMENTED SUBASSEMBLIES (INSER). EBR-II Project PDF Author:
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ISBN:
Category :
Languages : en
Pages :

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PNL-17

PNL-17 PDF Author:
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Category :
Languages : en
Pages :

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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.