ASTM E944-13
(Guide)Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
SIGNIFICANCE AND USE
3.1 Adjustment methods provide a means for combining the results of neutron transport calculations with neutron dosimetry measurements (see Test Method E1005 and NUREG/CR-5049) in order to obtain optimal estimates for neutron damage exposure parameters with assigned uncertainties. The inclusion of measurements reduces the uncertainties for these parameter values and provides a test for the consistency between measurements and calculations and between different measurements (see 3.3.3). This does not, however, imply that the standards for measurements and calculations of the input data can be lowered; the results of any adjustment procedure can be only as reliable as are the input data.
3.2 Input Data and Definitions :
3.2.1 The symbols introduced in this section will be used throughout the guide.
3.2.2 Dosimetry measurements are given as a set of reaction rates (or equivalent) denoted by the following symbols:
These data are, at present, obtained primarily from radiometric dosimeters, but other types of sensors may be included (see 4.1).
3.2.3 The neutron spectrum (see Terminology E170) at the dosimeter location, fluence or fluence rate Φ(E) as a function of neutron energy E , is obtained by appropriate neutronics calculations (neutron transport using the methods of discrete ordinates or Monte Carlo, see Guide E482). The results of the calculation are customarily given in the form of multigroup fluences or fluence rates.
where:
Ej and Ej+1 are the lower and upper bounds for the j-th energy group, respectively, and k is the total number of groups.
3.2.4 The reaction cross sections of the dosimetry sensors are obtained from an evaluated cross section file. The cross section for the i-th reaction as a function of energy E will be denoted by the following:
Used in connection with the group fluences, Eq 2, are the calculated group-averaged cross sections σij. These values are defined through the following equation:
...
SCOPE
1.1 This guide covers the analysis and interpretation of the physics dosimetry for Light Water Reactor (LWR) surveillance programs. The main purpose is the application of adjustment methods to determine best estimates of neutron damage exposure parameters and their uncertainties.
1.2 This guide is also applicable to irradiation damage studies in research reactors.
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.
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Designation: E944 − 13
Standard Guide for
Application of Neutron Spectrum Adjustment Methods in
1
Reactor Surveillance, E 706 (IIA)
This standard is issued under the fixed designation E944; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope E481 Test Method for Measuring Neutron Fluence Rates by
Radioactivation of Cobalt and Silver
1.1 This guide covers the analysis and interpretation of the
E482 Guide for Application of Neutron Transport Methods
physics dosimetry for LightWater Reactor (LWR) surveillance
for Reactor Vessel Surveillance, E706 (IID)
programs. The main purpose is the application of adjustment
E523 Test Method for Measuring Fast-Neutron Reaction
methods to determine best estimates of neutron damage expo-
Rates by Radioactivation of Copper
sure parameters and their uncertainties.
E526 Test Method for Measuring Fast-Neutron Reaction
1.2 This guide is also applicable to irradiation damage
Rates by Radioactivation of Titanium
studies in research reactors.
E693 Practice for Characterizing Neutron Exposures in Iron
1.3 This standard does not purport to address all of the and Low Alloy Steels in Terms of Displacements Per
safety concerns, if any, associated with its use. It is the
Atom (DPA), E 706(ID)
responsibility of the user of this standard to establish appro- E704 Test Method for Measuring Reaction Rates by Radio-
priate safety and health practices and determine the applica-
activation of Uranium-238
bility of regulatory limitations prior to use. E705 Test Method for Measuring Reaction Rates by Radio-
activation of Neptunium-237
2. Referenced Documents
E706 MasterMatrixforLight-WaterReactorPressureVessel
3
2
Surveillance Standards, E 706(0) (Withdrawn 2011)
2.1 ASTM Standards:
E844 Guide for Sensor Set Design and Irradiation for
E170 Terminology Relating to Radiation Measurements and
Reactor Surveillance, E 706 (IIC)
Dosimetry
E853 Practice forAnalysis and Interpretation of Light-Water
E262 Test Method for Determining Thermal Neutron Reac-
Reactor Surveillance Results, E706(IA)
tion Rates and Thermal Neutron Fluence Rates by Radio-
E854 Test Method for Application and Analysis of Solid
activation Techniques
State Track Recorder (SSTR) Monitors for Reactor
E263 Test Method for Measuring Fast-Neutron Reaction
Surveillance, E706(IIIB)
Rates by Radioactivation of Iron
E910 Test Method for Application and Analysis of Helium
E264 Test Method for Measuring Fast-Neutron Reaction
Accumulation Fluence Monitors for Reactor Vessel
Rates by Radioactivation of Nickel
Surveillance, E706 (IIIC)
E265 Test Method for Measuring Reaction Rates and Fast-
E1005 Test Method for Application and Analysis of Radio-
Neutron Fluences by Radioactivation of Sulfur-32
metric Monitors for Reactor Vessel Surveillance, E 706
E266 Test Method for Measuring Fast-Neutron Reaction
(IIIA)
Rates by Radioactivation of Aluminum
E1018 Guide for Application of ASTM Evaluated Cross
E393 Test Method for Measuring Reaction Rates by Analy-
Section Data File, Matrix E706 (IIB)
sis of Barium-140 From Fission Dosimeters
E2005 Guide for Benchmark Testing of Reactor Dosimetry
in Standard and Reference Neutron Fields
1
E2006 Guide for BenchmarkTesting of LightWater Reactor
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applicationsand is the direct responsibility of Subcommittee
Calculations
E10.05 on Nuclear Radiation Metrology. A brief overview of Guide E944 appears 4
2.2 Nuclear Regulatory Commission Documents:
in Master Matrix E706 in 5.3.1(IIA).
NUREG/CR-1861 PCA Experiments and Blind Test
Current edition approved Jan. 1, 2013. Published January 2013. Originally
approved in 1983. Last previous edition approved in 2008 as E944 – 08. DOI:
10.1520/E0944-13.
2 3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or The last approved version of this historical standard is referenced on
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM www.astm.org.
4
Standards volume information, refer to the standard’s Document Summary page on Available from Superintendents of Documents, U. S. Government Printing
the ASTM website. DOI: 10.1520/E0944-08. Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E944 − 13
NUREG/CR-2222 Theory and Practice of General Adjust- section for the i-th reaction as a function of energy E will be
ment and Model Fitting Procedures denoted by the following:
NUREG/CR-3318 LWR Pressure Ves
...
This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation: E944 − 08 E944 − 13
Standard Guide for
Application of Neutron Spectrum Adjustment Methods in
1
Reactor Surveillance, E 706 (IIA)
This standard is issued under the fixed designation E944; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope
1.1 This guide covers the analysis and interpretation of the physics dosimetry for Light Water Reactor (LWR) surveillance
programs. The main purpose is the application of adjustment methods to determine best estimates of neutron damage exposure
parameters and their uncertainties.
1.2 This guide is also applicable to irradiation damage studies in research reactors.
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.
2. Referenced Documents
2
2.1 ASTM Standards:
E170 Terminology Relating to Radiation Measurements and Dosimetry
E262 Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation
Techniques
E263 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron
E264 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel
E265 Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32
E266 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum
E343 Test Method for Measuring Reaction Rates by Analysis of Molybdenum-99 Radioactivity From Fission Dosimeters
3
(Withdrawn 2002)
E393 Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters
E481 Test Method for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver
E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
E523 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
E526 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Titanium
E693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA),
E 706(ID)
E704 Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
E705 Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
3
E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E 706(0) (Withdrawn 2011)
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC)
E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706(IA)
E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance,
E706(IIIB)
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applicationsand is the direct responsibility of Subcommittee E10.05 on Nuclear
Radiation Metrology. A brief overview of Guide E944 appears in Master Matrix E706 in 5.3.1(IIA).
Current edition approved Nov. 1, 2008Jan. 1, 2013. Published January 2009January 2013. Originally approved in 1983. Last previous edition approved in 20022008 as
E944 – 02.E944 – 08. DOI: 10.1520/E0944-08.10.1520/E0944-13.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website. DOI: 10.1520/E0944-08.
3
The last approved version of this historical standard is referenced on www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E944 − 13
E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance,
E706 (IIIC)
E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706 (IIIA)
E1018 Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB)
E2005 Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
E2006
...
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