An Examination of the Elastic Structural Response of the Advanced Neutron Source Fuel Plates 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 An Examination of the Elastic Structural Response of the Advanced Neutron Source Fuel Plates PDF full book. Access full book title An Examination of the Elastic Structural Response of the Advanced Neutron Source Fuel Plates by . Download full books in PDF and EPUB format.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 51
Get Book Here
Book Description
Procedures for evaluating the elastic structural response of the Advanced Neutron Source (ANS) fuel plates to coolant flow and to temperature variations are presented in this report. Calculations are made that predict the maximum deflection and the maximum stress for a representative plate from the upper and from the lower fuel elements.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 51
Get Book Here
Book Description
Procedures for evaluating the elastic structural response of the Advanced Neutron Source (ANS) fuel plates to coolant flow and to temperature variations are presented in this report. Calculations are made that predict the maximum deflection and the maximum stress for a representative plate from the upper and from the lower fuel elements.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 141
Get Book Here
Book Description
The thin fuel plates planned for the Advanced Neutron Source are to be cooled by forcing heavy water at high velocity, 25 m/s, through thin cooling channels on each side of each plate. Because the potential for structural failure of the plates is a design concern, considerable effort has been expended in assessing this potential. As part of this effort, experimental flow tests and analyses to evaluate the structural response of circular arc plates have been conducted, and the results are given in this report.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 67
Get Book Here
Book Description
The reactor for the planned Advanced Neutron Source uses closely spaced plates cooled by heavy water flowing through narrow channels. Two sets of tests were performed on the upper and lower fuel plates for the structural response of the fuel plates to the required high coolant flow velocities. This report contains the data from the second round of tests. Results and conclusions from all of the tests are also included in this report. The tests were done using light water on full-scale epoxy models, and through model theory, the results were related to the prototype plates, which are aluminum-clad aluminum/uranium silicide involute-shaped plates.
Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 936
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 654
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 54
Get Book Here
Book Description
The thin aluminum-clad fuel plates proposed for the Advanced Neutron Source reactor are stressed by the high-velocity coolant flowing on each side of the plates and by the thermal gradients in the plates. The total stress, composed of the sum of the flow stress and the thermal stress at a point, could be reduced if the thermal loads tend to relax when the stress magnitude approaches the yield stress of the material. The potential of this occurring would be very significant in assessing the structural reliability of the fuel plates and has been investigated through experiment. The results of this investigation are given in this report.
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 730
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 48
Get Book Here
Book Description
The planned reactor for the Advanced Neutron Source (ANS) will use closely spaced arrays of involute-shaped fuel plates that will be cooled by water flowing through the channels between the plates. There is concern that at certain coolant flow velocities, adjacent plates may deflect and touch, with resulting failure of the plates. Experiments have been conducted at the Oak Ridge National Laboratory to examine this potential phenomenon. Results of the experiments and comparison with analytical predictions are reported. The tests were conducted using full-scale epoxy plate models of the aluminum/uranium silicide ANS involute-shaped fuel plates. Use of epoxy plates and model theory allowed lower flow velocities and pressures to explore the potential failure mechanism. Plate deflections and channel pressures as functions of the flow velocity are examined. Comparisons with mathematical models are noted.
Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 704
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 43
Get Book Here
Book Description
The reactor for the planned Advanced Neutron Source will use closely spaced arrays of fuel plates. The plates are thin and will have a core containing enriched uranium silicide fuel clad in aluminum. The heat load caused by the nuclear reactions within the fuel plates will be removed by flowing high-velocity heavy water through narrow channels between the plates. However, the plates will still be at elevated temperatures while in service, and the potential for excessive plate deformation because of creep must be considered. An analysis to include creep for deformation and stresses because of temperature over a given time span has been performed and is reported herein.
