There is no PDF download available at this time, however you may purchase a copy of this document from the IHS Standards Store
Standard
Withdrawn, No replacement
Last Updated: Dec 31, 2010
Track Document
ASTM E453-79(2001)
Standard Practice for Examination of Fuel Element Cladding Including the Determination of the Mechanical Properties (Withdrawn 2008)
Standard Practice for Examination of Fuel Element Cladding Including the Determination of the Mechanical Properties (Withdrawn 2008)
E0453-79R01
ASTM|E0453-79R01|en-US
Standard Practice for Examination of Fuel Element Cladding Including the Determination of the Mechanical Properties (Withdrawn 2008)
Standard
E453 Standard Practice for Examination of Fuel Element Cladding Including the Determination of the Mechanical Properties (Withdrawn 2008)>
new
BOS Vol. 12.02 Committee E10
$
0.00
Out of stock
Significance and Use
The physical and mechanical properties of cladding materials can be altered by exposure to a high-energy neutron flux. The magnitude and relationship of these changes are functions of the material and its metallurgical condition; the amount, rate, and energy spectrum of the radiation; the exposure temperature; the test temperature; the purity, velocity, volume, and purification system of the coolant; and effects of contained fuel.
Scope
1.1 This practice covers the procedures for postirradiation examination of cladding, determination of breached nuclear fuel elements, selection of material and tests for radiation studies, determination of radiation conditions, conduction of tests for mechanical properties of cladding, and the reporting of data.
1.2 The purpose of this practice is to provide detailed guidelines for the postirradiation examination of fuel element cladding and to achieve better correlation and interpretation of the data in the field of radiation effects.
1.3 This practice may be applied to metallic cladding from all types of fuel elements. The tests described in this practice for determining mechanical properties of the fuel element cladding practice should be included in the preirradiation characterization of the cladding and for planning irradiation effects tests for evaluation of materials for cladding and other components in nuclear reactors.
Note 1—The values stated in SI units as described in Standard E 380 are to be regarded as the standard.