ASTM E944-19
(Guide)Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
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This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the
Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
Designation: E944 − 19
Standard Guide for
Application of Neutron Spectrum Adjustment Methods in
1
Reactor Surveillance
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 E265 Test Method for Measuring Reaction Rates and Fast-
Neutron Fluences by Radioactivation of Sulfur-32
1.1 This guide covers the analysis and interpretation of the
E266 Test Method for Measuring Fast-Neutron Reaction
physics dosimetry for LightWater Reactor (LWR) surveillance
Rates by Radioactivation of Aluminum
programs. The main purpose is the application of adjustment
E393 Test Method for Measuring Reaction Rates by Analy-
methods to determine best estimates of neutron damage expo-
sis of Barium-140 From Fission Dosimeters
sure parameters and their uncertainties.
E481 Test Method for Measuring Neutron Fluence Rates by
1.2 This guide is also applicable to irradiation damage
Radioactivation of Cobalt and Silver
studies in research reactors.
E482 Guide for Application of Neutron Transport Methods
1.3 This standard does not purport to address all of the
for Reactor Vessel Surveillance
safety concerns, if any, associated with its use. It is the
E523 Test Method for Measuring Fast-Neutron Reaction
responsibility of the user of this standard to establish appro-
Rates by Radioactivation of Copper
priate safety, health, and environmental practices and deter-
E526 Test Method for Measuring Fast-Neutron Reaction
mine the applicability of regulatory limitations prior to use.
Rates by Radioactivation of Titanium
1.4 This international standard was developed in accor-
E693 Practice for Characterizing Neutron Exposures in Iron
dance with internationally recognized principles on standard-
and Low Alloy Steels in Terms of Displacements Per
ization established in the Decision on Principles for the
Atom (DPA)
Development of International Standards, Guides and Recom-
E704 Test Method for Measuring Reaction Rates by Radio-
mendations issued by the World Trade Organization Technical
activation of Uranium-238
Barriers to Trade (TBT) Committee.
E705 Test Method for Measuring Reaction Rates by Radio-
2. Referenced Documents
activation of Neptunium-237
2
E706 MasterMatrixforLight-WaterReactorPressureVessel
2.1 ASTM Standards:
E170 Terminology Relating to Radiation Measurements and Surveillance Standards
Dosimetry E844 Guide for Sensor Set Design and Irradiation for
E262 Test Method for Determining Thermal Neutron Reac-
Reactor Surveillance
tion Rates and Thermal Neutron Fluence Rates by Radio-
E853 Practice forAnalysis and Interpretation of Light-Water
activation Techniques
Reactor Surveillance Neutron Exposure Results
E263 Test Method for Measuring Fast-Neutron Reaction
E854 Test Method for Application and Analysis of Solid
Rates by Radioactivation of Iron
State Track Recorder (SSTR) Monitors for Reactor Sur-
E264 Test Method for Measuring Fast-Neutron Reaction
veillance
Rates by Radioactivation of Nickel
E910 Test Method for Application and Analysis of Helium
Accumulation Fluence Monitors for Reactor Vessel Sur-
veillance
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
E1005 Test Method for Application and Analysis of Radio-
Technology and Applications and is the direct responsibility of Subcommittee
E10.05 on Nuclear Radiation Metrology. A brief overview of Guide E944 appears metric Monitors for Reactor Vessel Surveillance
in Master Matrix E706 in 5.4.1.
E1018 Guide for Application of ASTM Evaluated Cross
Current edition approved Oct. 1, 2019. Published October 2019. Originally
ɛ1 Section Data File
approved in 1983. Last previous edition approved in 2013 as E944 – 13 . DOI:
10.1520/E0944-19. E2005 Guide for Benchmark Testing of Reactor Dosimetry
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
in Standard and Reference Neutron Fields
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
E2006 Guide for BenchmarkTesting of LightWater Reactor
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. Calculations
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E944 − 19
3
2.2 Nuclear Regulatory Commission Documents: where:
NUREG/CR-1861 PCA Experiments and Blind Test E and E are the lower and upper boun
...
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.
´1
Designation: E944 − 13 E944 − 19
Standard Guide for
Application of Neutron Spectrum Adjustment Methods in
1
Reactor Surveillance
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
ε NOTE—The title of this guide and the Referenced Documents were updated editorially in May 2017.
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 safety, health, and healthenvironmental practices and determine the
applicability of regulatory limitations prior to use.
1.4 This international standard was developed in accordance with internationally recognized principles on standardization
established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued
by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
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
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
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)
E704 Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
E705 Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance
E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance
E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance
E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.05 on Nuclear
Radiation Metrology. A brief overview of Guide E944 appears in Master Matrix E706 in 5.4.1.
Current edition approved Jan. 1, 2013Oct. 1, 2019. Published January 2013October 2019. Originally approved in 1983. Last previous edition approved in 20082013 as
ɛ1
E944 – 08.E944 – 13 . DOI: 10.1520/E0944-13E01.10.1520/E0944-19.
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.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E944 − 19
E1018 Guide for Application of ASTM Evaluated Cross Section D
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