ASTM E944-13e1

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 and health 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.

General Information

• Status: Historical
• Publication Date: 31-Dec-2012
• ICS: 27.120.20 - Nuclear power plants. Safety
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.05 - Nuclear Radiation Metrology

Relations

• Replaces: ASTM E944-13 - Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
• Effective Date: 01-Jan-2013
• Replaced By: ASTM E944-19 - Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
• Effective Date: 01-Oct-2019
• Referred By: ASTM E1854-19 - Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts
• Effective Date: 01-Jan-2013
• Referred By: ASTM E704-19 - Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
• Effective Date: 01-Jan-2013
• Referred By: ASTM E1005-21 - Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
• Effective Date: 01-Jan-2013
• Referred By: ASTM E720-23 - Standard Guide for Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness Testing of Electronics
• Effective Date: 01-Jan-2013
• Referred By: ASTM E261-16(2021) - Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
• Effective Date: 01-Jan-2013
• Referred By: ASTM E265-15(2020) - Standard Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32
• Effective Date: 01-Jan-2013
• Referred By: ASTM E705-18 - Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
• Effective Date: 01-Jan-2013
• Referred By: ASTM E722-19 - Standard Practice for Characterizing Neutron Fluence Spectra in Terms of an Equivalent Monoenergetic Neutron Fluence for Radiation-Hardness Testing of Electronics
• Effective Date: 01-Jan-2013
• Referred By: ASTM E2956-23 - Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
• Effective Date: 01-Jan-2013
• Referred By: ASTM E1855-20 - Standard Test Method for Use of 2N2222A Silicon Bipolar Transistors as Neutron Spectrum Sensors and Displacement Damage Monitors
• Effective Date: 01-Jan-2013
• Referred By: ASTM E2059-20 - Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry
• Effective Date: 01-Jan-2013
• Referred By: ASTM E900-21 - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
• Effective Date: 01-Jan-2013
• Referred By: ASTM E523-21e1 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
• Effective Date: 01-Jan-2013

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
´1
Designation: E944 − 13
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 E264 Test Method for Measuring Fast-Neutron Reaction
Rates by Radioactivation of Nickel
1.1 This guide covers the analysis and interpretation of the
E265 Test Method for Measuring Reaction Rates and Fast-
physics dosimetry for LightWater Reactor (LWR) surveillance
Neutron Fluences by Radioactivation of Sulfur-32
programs. The main purpose is the application of adjustment
E266 Test Method for Measuring Fast-Neutron Reaction
methods to determine best estimates of neutron damage expo-
Rates by Radioactivation of Aluminum
sure parameters and their uncertainties.
E393 Test Method for Measuring Reaction Rates by Analy-
1.2 This guide is also applicable to irradiation damage
sis of Barium-140 From Fission Dosimeters
studies in research reactors.
E481 Test Method for Measuring Neutron Fluence Rates by
1.3 This standard does not purport to address all of the
Radioactivation of Cobalt and Silver
safety concerns, if any, associated with its use. It is the
E482 Guide for Application of Neutron Transport Methods
responsibility of the user of this standard to establish appro-
for Reactor Vessel Surveillance
priate safety and health practices and determine the applica-
E523 Test Method for Measuring Fast-Neutron Reaction
bility of regulatory limitations prior to use.
Rates by Radioactivation of Copper
1.4 This international standard was developed in accor-
E526 Test Method for Measuring Fast-Neutron Reaction
dance with internationally recognized principles on standard-
Rates by Radioactivation of Titanium
ization established in the Decision on Principles for the
E693 Practice for Characterizing Neutron Exposures in Iron
Development of International Standards, Guides and Recom-
and Low Alloy Steels in Terms of Displacements Per
mendations issued by the World Trade Organization Technical
Atom (DPA)
Barriers to Trade (TBT) Committee.
E704 Test Method for Measuring Reaction Rates by Radio-
activation of Uranium-238
2. Referenced Documents
E705 Test Method for Measuring Reaction Rates by Radio-
2
2.1 ASTM Standards: activation of Neptunium-237
E706 MasterMatrixforLight-WaterReactorPressureVessel
E170 Terminology Relating to Radiation Measurements and
Dosimetry Surveillance Standards
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 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-
veillance
1 E910 Test Method for Application and Analysis of Helium
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applicationsand is the direct responsibility of Subcommittee
Accumulation Fluence Monitors for Reactor Vessel Sur-
E10.05 on Nuclear Radiation Metrology. A brief overview of Guide E944 appears
veillance
in Master Matrix E706 in 5.4.1.
E1005 Test Method for Application and Analysis of Radio-
Current edition approved Jan. 1, 2013. Published January 2013. Originally
metric Monitors for Reactor Vessel Surveillance
approved in 1983. Last previous edition approved in 2008 as E944 – 08. DOI:
10.1520/E0944-13E01.
E1018 Guide for Application of ASTM Evaluated Cross
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Section Data File
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
E2005 Guide for Benchmark Testing of Reactor Dosimetry
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. DOI: 10.1520/E0944-08. in Standard and Reference Neutron Fields
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
´1
E944 − 13
E2006 Guide for BenchmarkTesting of LightWater Reactor where:
Calculations E and E are the lower and upper bounds for the j-th energy
j j+1
3
group, respectively, and k is the total number of groups.
2.2 Nuclear Regulatory Commission Documents:
NUREG/CR-1861 PCA Exp
...

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 − 13
Standard Guide for
Application of Neutron Spectrum Adjustment Methods in
1
Reactor Surveillance, E 706 (IIA)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 and health 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 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,
E706 (IIIC)Surveillance
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).5.4.1.
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/E0944-13.10.1520/E0944-13E01.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at [e-mail]. 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 ----------------------
´1
E944 − 13
E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
E1018 Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (II
...