The Design and Construction of the EBR-II Initial Fuel Loading Facility PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download The Design and Construction of the EBR-II Initial Fuel Loading Facility PDF full book. Access full book title The Design and Construction of the EBR-II Initial Fuel Loading Facility by . Download full books in PDF and EPUB format.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The need for the first core for EBR-11 resulted in the design and construction of the Initial Fuel Loading Facility for this reactor. The plant was built to provide the required initial loading, to train personnel, and to test prototype equipment for the remote reprocessing of fuel materials in the EBR- II Fuel Cycle Facility. The facilities include: remotely manipulated melting, casting, and pin processing equipment, a degreaser, hoods and their atmospheric control system, a gas-purification system, fuelelement-assembly equipment, mold- preparation and balance room, bonding furnaces, a maintenance shop, and a change area. (auth).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The need for the first core for EBR-11 resulted in the design and construction of the Initial Fuel Loading Facility for this reactor. The plant was built to provide the required initial loading, to train personnel, and to test prototype equipment for the remote reprocessing of fuel materials in the EBR- II Fuel Cycle Facility. The facilities include: remotely manipulated melting, casting, and pin processing equipment, a degreaser, hoods and their atmospheric control system, a gas-purification system, fuelelement-assembly equipment, mold- preparation and balance room, bonding furnaces, a maintenance shop, and a change area. (auth).
Author: James E. Ayer Publisher: ISBN: Category : Nuclear power plants Languages : en Pages : 50
Book Description
The need for the first core for EBR-II resulted in the design and construction of the Initial Fuel Loading Facility for this reactor. The plant was built to provide the required initial loading, to train personnel, and to test prototype equipment for the remote reprocessing of fuel materials in the EBR- II Fuel Cycle Facility. The facilities include: remotely manipulated melting, casting, and pin processing equipment, a degreaser, hoods and their atmospheric control system, a gas-purification system, fuel-element-assembly equipment, mold- preparation and balance room, bonding furnaces, a maintenance shop, and a change area.
Author: Publisher: ISBN: Category : Languages : en Pages : 66
Book Description
Experimental Breeder Reactor No. II (EBR-II), initially designed, built, and operated as a demonstration fast-neutron power reactor with an integral fuel cycle facility, has been operated as an LMFBR irradiation test facility for approximately the past fourteen years. The initial core loading and subsequent fuel has been fabricated by Argonne National Laboratory and two commercial vendors. Fuel-fabrication techniques, equipment, and procedures currently in use were originally developed for the recycle of irradiated EBR-II fuel in the remotely operated ANL Fuel Cycle Facility. Fuel-element design has undergone several changes to obtain better performance and extended burnup. Correspondingly, fuel-fabrication techniques have been modified and refined, and the process has been placed in conformance with new administrative, safety, quality-assurance, and safeguards requirements.
Author: L. J. Koch Publisher: ISBN: Category : Breeder reactors Languages : en Pages : 334
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.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The Argoune Experimentul Breeder Reactor-II is a completely integrated nuclear power plant which employs an unmoderated reactor as a heat source, and generates 20,000 kw of electricity. The integrated nuclear plant includes the fuel re-processing and fabrication cycle and thereby makes a signigicant contribution to power reactor techaology by operating on recycled fuel. The preliminary design of this plant was described at the First International Conference on the Peaceful Uses of Atomic Energy in 1955. Although the basic design concept and objectives have remained unchanged, many modiflcations have been made in the detailed design, including separation of the facility into several plants and providing containment for the reaetor system. The plant capacity and basic power cycle have rematned essentially unchanged: 62.5 Mw thermal, 900F reactor sodium outlet temperature, and 1250-psig steam at 850F at the turbine throttle. The feed-water te mperature, however, has been increased to 550F to reduce thermal stresses in the steam generator. (auth).
Author: Publisher: ISBN: Category : Metallurgy Languages : en Pages : 44
Book Description
Activities in a program to assemble and test jacketed fuel rods and multi-rod fuel rod assemblies for EBR-II are reported. Other work is reported on evaluation of the manufacturing techniques proposed for the EBR-II cycle in a sustained operation and on remotely operable equipment under production conditions. Data on fabrication and assembly of fuel rods and assemblies are included. A total of 10,781 fully inspected fuel rods were fabricated for EBR-II core by processes adaptable to remote operation.
Author: W. B. Loewenstein Publisher: ISBN: Category : Breeder reactors Languages : en Pages : 78
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.
Author: J. C. Hesson Publisher: ISBN: Category : Breeder reactors Languages : en Pages : 200
Book Description
Operations may be described in general terms as including disassembly of reactor subassemblies and their constituent fuel elements, fuel purification, refabrication of fuel elements, and reassembly of the reactor core subassemblies for reloading into the reactor.
Author: 
Author: 
Author: James E. Ayer
Author: 
Author: L. J. Koch
Author: 
Author: 
Author: 
Author: 
Author: W. B. Loewenstein
Author: J. C. Hesson