ASTM E 560 : 2001
Withdrawn
A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.
Standard Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E706(IC) (Withdrawn 2009)
Hardcopy , PDF
30-04-2009
English
10-06-2001
CONTAINED IN VOL. 12.02, 2008 Outlines analytical and analytical experimental approaches that may be used to determine the variation in neutron exposure and exposure rate and energy spectrum between surveillance locations and points in the pressure vessel wall.
Committee |
E 10
|
DocumentType |
Standard Practice
|
Pages |
6
|
PublisherName |
American Society for Testing and Materials
|
Status |
Withdrawn
|
Supersedes |
1.1 This practice covers analytical and analytical-experimental approaches that can be used to determine the variation in neutron exposure (fluence E > 1.0 MeV, dpa, etc.) and exposure rate and energy spectrum between surveillance locations and points in the pressure vessel wall. Procedures for reporting the results of these analyses with assigned uncertainties are also suggested. This practice deals with the physics-dosimetry aspects of surveillance programs and must be used in conjunction with other Matrix E 706 standards to provide extrapolations based on metallurgical damage correlations.
1.2 The physics-dosimetry relationships determined from this practice may be used to estimate pressure vessel damage through application of Practice E 693 and Guide E 900 standards, using fluence (E > 1.0 MeV), dpa, or damage function derived exposure parameters as independent exposure variables. Supporting the application of these standards is E 944, E 1018, E 1005, and E 854 standards, identified in 2.1.
1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.
ASTM E 1018 : 2009 | Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB) |
ASTM E 1018 : 2009 : R2013 : EDT 1 | Standard Guide for Application of ASTM Evaluated Cross Section Data File |
ASTM E 1018 : 2009 : R2013 | Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB) |
ASTM E 706 : 2016 | Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards |
ASTM E 482 : 2016 : REDLINE | Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance |
ASTM E 693 : 2017 : REDLINE | Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA) |
ASTM E 170 : 2017 : REDLINE | Standard Terminology Relating to Radiation Measurements and Dosimetry |
ASTM E 854 : 2014-12 | TEST METHOD FOR APPLICATION AND ANALYSIS OF SOLID STATE TRACK RECORDER (SSTR) MONITORS FOR REACTOR SURVEILLANCE |
ASTM E 184 : 1979 : R1994 | Standard Practice for Effects of High-Energy Neutron Radiation on the Mechanical Properties of Metallic Materials, E706 (IB) (Withdrawn 2002) |
ASTM E 185 : 2016 : REDLINE | Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels |
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