ASTM E 560 Standard Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E 706(IC)
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ASTM E 560 Document Information:
Title
Standard Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E 706(IC)
ASTM International
Publication Date:
Jun 10, 2001
Scope:
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.
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.
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.
Keywords:
- damage correlations
- dosimetry
- dpa
- exposure parameters
- pressure vessel
- surveillance
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