Author: E. A. Lees
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 88
Book Description
Fabrication of Fuel Elements by Swaging
Author: E. A. Lees
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 88
Book Description
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 88
Book Description
The Integral Fabrication of Uranium Dioxide Fuel Elements by Rotary Swaging
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The feasibility of fabricating UO/sub 2/ fuel elements having densities of 90% theoretical by rotary swaging inside a Zircaloy or stainless steel sheath has been demonstrated. The results show that the density achieved in this process is a function both of the type of UO/sub 2/ used and the mechanical properties of the sheathing material. (auth).
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The feasibility of fabricating UO/sub 2/ fuel elements having densities of 90% theoretical by rotary swaging inside a Zircaloy or stainless steel sheath has been demonstrated. The results show that the density achieved in this process is a function both of the type of UO/sub 2/ used and the mechanical properties of the sheathing material. (auth).
Nuclear Reactor Fuel Elements
Author: Albert R. Kaufmann
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 760
Book Description
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 760
Book Description
The Integral Fabrication of Uranium Dioxide Fuel Elements by Rotary Swaging
Fabrication of Uranium Oxide Fuel Elements
Author: G. Rolland Cole
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 40
Book Description
Experimental fuel elements of UO2 clad in metallic sheaths were fabricated by swaging, rolling, and coextrusion. The effects of the type of UO2 and of the materials and dimensions of the sheath were investigated. Fused UO2 swaged in stainless steel tubing reached a maximum density of 93% of theoretical.
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 40
Book Description
Experimental fuel elements of UO2 clad in metallic sheaths were fabricated by swaging, rolling, and coextrusion. The effects of the type of UO2 and of the materials and dimensions of the sheath were investigated. Fused UO2 swaged in stainless steel tubing reached a maximum density of 93% of theoretical.
The Fabrication of the Fuel Elements for the UO2 High Burn-up Program
Author: E. A. Lees
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 34
Book Description
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 34
Book Description
Investigation of Stretch-forming Process for Fabrication of Reactor Fuel Elements
Author: M. D'Amore
Publisher:
ISBN:
Category : Metal stamping
Languages : en
Pages : 42
Book Description
Three methods of manufacturing fuel rods were investigated. The methods studied were: swaging, stretch-forming, compartmenting by stretch-forming.
Publisher:
ISBN:
Category : Metal stamping
Languages : en
Pages : 42
Book Description
Three methods of manufacturing fuel rods were investigated. The methods studied were: swaging, stretch-forming, compartmenting by stretch-forming.
Fabrication of Fuel Elements
Author: Gerhard Matz
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 88
Book Description
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 88
Book Description
Process Development and Fabrication of Th--7.6 Wt % U Fuel Elements for the Second Core Loading of the Sodium Reactor Experiment
Author: J. A. Stanley
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 34
Book Description
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 34
Book Description
Analysis of the ATR Fuel Element Swaging Process
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 250
Book Description
This report documents a detailed evaluation of the swaging process used to connect fuel plates to side plates in Advanced Test Reactor (ATR) fuel elements. The swaging is a mechanical process that begins with fitting a fuel plate into grooves in the side plates. Once a fuel plate is positioned, a lip on each of two side plate grooves is pressed into the fuel plate using swaging wheels to form the joints. Each connection must have a specified strength (measured in terms, of a pullout force capacity) to assure that these joints do not fail during reactor operation. The purpose of this study is to analyze the swaging process and associated procedural controls, and to provide recommendations to assure that the manufacturing process produces swaged connections that meet the minimum strength requirement. The current fuel element manufacturer, Babcock and Wilcox (B & W) of Lynchburg, Virginia, follows established procedures that include quality inspections and process controls in swaging these connections. The procedures have been approved by Lockheed Martin Idaho Technologies and are designed to assure repeatability of the process and structural integrity of each joint. Prior to July 1994, ATR fuel elements were placed in the Hydraulic Test Facility (HTF) at the Idaho National Engineering Laboratory (AGNAIL), Test Reactor Area (TRA) for application of Boehmite (an aluminum oxide) film and for checking structural integrity before placement of the elements into the ATR. The results presented in this report demonstrate that the pullout strength of the swaged connections is assured by the current manufacturing process (with several recommended enhancements) without the need for- testing each element in the HTF.
Publisher:
ISBN:
Category :
Languages : en
Pages : 250
Book Description
This report documents a detailed evaluation of the swaging process used to connect fuel plates to side plates in Advanced Test Reactor (ATR) fuel elements. The swaging is a mechanical process that begins with fitting a fuel plate into grooves in the side plates. Once a fuel plate is positioned, a lip on each of two side plate grooves is pressed into the fuel plate using swaging wheels to form the joints. Each connection must have a specified strength (measured in terms, of a pullout force capacity) to assure that these joints do not fail during reactor operation. The purpose of this study is to analyze the swaging process and associated procedural controls, and to provide recommendations to assure that the manufacturing process produces swaged connections that meet the minimum strength requirement. The current fuel element manufacturer, Babcock and Wilcox (B & W) of Lynchburg, Virginia, follows established procedures that include quality inspections and process controls in swaging these connections. The procedures have been approved by Lockheed Martin Idaho Technologies and are designed to assure repeatability of the process and structural integrity of each joint. Prior to July 1994, ATR fuel elements were placed in the Hydraulic Test Facility (HTF) at the Idaho National Engineering Laboratory (AGNAIL), Test Reactor Area (TRA) for application of Boehmite (an aluminum oxide) film and for checking structural integrity before placement of the elements into the ATR. The results presented in this report demonstrate that the pullout strength of the swaged connections is assured by the current manufacturing process (with several recommended enhancements) without the need for- testing each element in the HTF.