The EBR-II Fuel Cycle Story

The EBR-II Fuel Cycle Story PDF Author: Charles E. Stevenson
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 274

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Book Description
In this comprehensive volume, Stevenson recounts the history of the Experimental Breeder Reactor-II (EBR-II), the Fuel Cycle Facility (FCF), and the process requirements of this unique technology. The author also explains the reasons behind the remarkable success of both the EBR-II and the FCF. These data, presented as a useful information source, should be of considerable significance to the continuing development of nuclear power.

The EBR-II Fuel Cycle Story

The EBR-II Fuel Cycle Story PDF Author: Charles E. Stevenson
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 274

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Book Description
In this comprehensive volume, Stevenson recounts the history of the Experimental Breeder Reactor-II (EBR-II), the Fuel Cycle Facility (FCF), and the process requirements of this unique technology. The author also explains the reasons behind the remarkable success of both the EBR-II and the FCF. These data, presented as a useful information source, should be of considerable significance to the continuing development of nuclear power.

Nuclear Criticality Control in the EBR-II Fuel Cycle Facility

Nuclear Criticality Control in the EBR-II Fuel Cycle Facility PDF Author: J. C. Hesson
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 40

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Book Description
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.

FUEL MANAGEMENT AND INVENTORY IN THE EBR-II FUEL CYCLE.

FUEL MANAGEMENT AND INVENTORY IN THE EBR-II FUEL CYCLE. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description


The Design and Construction of the EBR-II Initial Fuel Loading Facility

The Design and Construction of the EBR-II Initial Fuel Loading Facility PDF Author: James E. Ayer
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 50

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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.

EBR-II Spent Fuel Treatment Demonstration Project

EBR-II Spent Fuel Treatment Demonstration Project PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 7

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Book Description
For approximately 10 years, Argonne National Laboratory was developed a fast reactor fuel cycle based on dry processing. When the US fast reactor program was canceled in 1994, the fuel processing technology, called the electrometallurgical technique, was adapted for treating unstable spent nuclear fuel for disposal. While this technique, which involves electrorefining fuel in a molten salt bath, is being developed for several different fuel categories, its initial application is for sodium-bonded metallic spent fuel. In June 1996, the Department of Energy (DOE) approved a radiation demonstration program in which 100 spent driver assemblies and 25 spent blanket assemblies from the Experimental Breeder Reactor-II (EBR-II) will be treated over a three-year period. This demonstrated will provide data that address issues in the National Research Council's evaluation of the technology. The planned operations will neutralize the reactive component (elemental sodium) in the fuel and produce a low enriched uranium product, a ceramic waste and a metal waste. The fission products and transuranium elements, which accumulate in the electrorefining salt, will be stabilized in the glass-bonded ceramic waste form. The stainless steel cladding hulls, noble metal fission products, and insoluble residues from the process will be stabilized in a stainless steel/zirconium alloy. Upon completion of a successful demonstration and additional environmental evaluation, the current plans are to process the remainder of the DOE sodium bonded fuel.

Fabrication of Driver-fuel Elements for EBR-II.

Fabrication of Driver-fuel Elements for EBR-II. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 66

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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.

The Design and Construction of the EBR-II Initial Fuel Loading Facility

The Design and Construction of the EBR-II Initial Fuel Loading Facility PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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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).

IFR Fuel Cycle Demonstration in the EBR-II Fuel Cycle Facility

IFR Fuel Cycle Demonstration in the EBR-II Fuel Cycle Facility PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 11

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Book Description


Revised EBR-II Flowsheet for Fuel Cycle with Fuel Purification by Oxidative Slagging

Revised EBR-II Flowsheet for Fuel Cycle with Fuel Purification by Oxidative Slagging PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Experience with Lifetime Limits for EBR-II Core Components

Experience with Lifetime Limits for EBR-II Core Components PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
The Experimental Breeder Reactor No. 2 (EBR-II) is operated for the US Department of Energy by Argonne National Laboratory and is located on the Idaho National Engineering Laboratory where most types of American reactor were originally tested. EBR-II is a complete electricity-producing power plant now in its twenty-fourth year of successful operation. During this long history the reactor has had several concurrent missions, such as demonstration of a closed Liquid-Metal Reactor (LMR) fuel cycle (1964-69); as a steady-state irradiation facility for fuels and materials (1970 onwards); for investigating effects of operational transients on fuel elements (from 1981); for research into the inherent safety aspects of metal-fueled LMR's (from 1983); and, most recently, for demonstration of the Integral Fast Reactor (IFR) concept using U-Pu-Zr fuels. This paper describes experience gained at EBR-II in defining lifetime limits for LMR core components, particularly fuel elements.