ASTM E944-08

Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E706 (IIA)

SIGNIFICANCE AND USE
Adjustment methods provide a means for combining the results of neutron transport calculations with neutron dosimetry measurements (see Test Method E 1005 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.
Input Data and Definitions:  
The symbols introduced in this section will be used throughout the guide.
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).
The neutron spectrum (see Terminology E 170) 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 E 482). The results of the calculation are customarily given in the form of k group fluences or fluence rates.
where:
Ej and Ej+1  are the lower and upper bounds for the j-th energy group, respectively.
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:
Uncertainty information in the form of variances and covariances must be provide...
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.

General Information

• Status: Historical
• Publication Date: 31-Oct-2008
• 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 E944-02 - Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E706 (IIA)
• Effective Date: 01-Nov-2008
• Replaced By: ASTM E944-13 - Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
• 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-Nov-2008
• Referred By: ASTM E853-23 - Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
• Effective Date: 01-Nov-2008
• Referred By: ASTM E900-21 - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
• Effective Date: 01-Nov-2008
• 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-Nov-2008
• Referred By: ASTM E261-16(2021) - Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
• Effective Date: 01-Nov-2008
• Referred By: ASTM E482-22 - Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
• Effective Date: 01-Nov-2008
• Referred By: ASTM E1854-19 - Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts
• Effective Date: 01-Nov-2008
• Referred By: ASTM E1297-18 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
• Effective Date: 01-Nov-2008
• Referred By: ASTM E721-22 - Standard Guide for Determining Neutron Energy Spectra from Neutron Sensors for Radiation-Hardness Testing of Electronics
• Effective Date: 01-Nov-2008
• Referred By: ASTM E523-21e1 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
• Effective Date: 01-Nov-2008
• Referred By: ASTM E1035-18(2023) - Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
• Effective Date: 01-Nov-2008
• Referred By: ASTM E1006-21 - Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
• Effective Date: 01-Nov-2008
• Referred By: ASTM E1005-21 - Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
• Effective Date: 01-Nov-2008

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
Designation: E944 − 08
StandardGuide 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.
3
1. Scope simeters (Withdrawn 2002)
E393 Test Method for Measuring Reaction Rates by Analy-
1.1 This guide covers the analysis and interpretation of the
sis of Barium-140 From Fission Dosimeters
physics dosimetry for LightWater Reactor (LWR) surveillance
E481 Test Method for Measuring Neutron Fluence Rates by
programs. The main purpose is the application of adjustment
Radioactivation of Cobalt and Silver
methods to determine best estimates of neutron damage expo-
E482 Guide for Application of Neutron Transport Methods
sure parameters and their uncertainties.
for Reactor Vessel Surveillance, E706 (IID)
1.2 This guide is also applicable to irradiation damage
E523 Test Method for Measuring Fast-Neutron Reaction
studies in research reactors.
Rates by Radioactivation of Copper
1.3 This standard does not purport to address all of the E526 Test Method for Measuring Fast-Neutron Reaction
safety concerns, if any, associated with its use. It is the
Rates by Radioactivation of Titanium
responsibility of the user of this standard to establish appro- E693 Practice for Characterizing Neutron Exposures in Iron
priate safety and health practices and determine the applica-
and Low Alloy Steels in Terms of Displacements Per
bility of regulatory limitations prior to use. Atom (DPA), E 706(ID)
E704 Test Method for Measuring Reaction Rates by Radio-
2. Referenced Documents
activation of Uranium-238
2
E705 Test Method for Measuring Reaction Rates by Radio-
2.1 ASTM Standards:
activation of Neptunium-237
E170 Terminology Relating to Radiation Measurements and
E706 MasterMatrixforLight-WaterReactorPressureVessel
Dosimetry
3
Surveillance Standards, E 706(0) (Withdrawn 2011)
E262 Test Method for Determining Thermal Neutron Reac-
E844 Guide for Sensor Set Design and Irradiation for
tion Rates and Thermal Neutron Fluence Rates by Radio-
Reactor Surveillance, E 706 (IIC)
activation Techniques
E853 PracticeforAnalysisandInterpretationofLight-Water
E263 Test Method for Measuring Fast-Neutron Reaction
Reactor Surveillance Results, E706(IA)
Rates by Radioactivation of Iron
E854 Test Method for Application and Analysis of Solid
E264 Test Method for Measuring Fast-Neutron Reaction
State Track Recorder (SSTR) Monitors for Reactor
Rates by Radioactivation of Nickel
Surveillance, E706(IIIB)
E265 Test Method for Measuring Reaction Rates and Fast-
E910 Test Method for Application and Analysis of Helium
Neutron Fluences by Radioactivation of Sulfur-32
Accumulation Fluence Monitors for Reactor Vessel
E266 Test Method for Measuring Fast-Neutron Reaction
Surveillance, E706 (IIIC)
Rates by Radioactivation of Aluminum
E1005 Test Method for Application and Analysis of Radio-
E343 Test Method for Measuring Reaction Rates by Analy-
metric Monitors for Reactor Vessel Surveillance, E 706
sis of Molybdenum-99 Radioactivity From Fission Do-
(IIIA)
E1018 Guide for Application of ASTM Evaluated Cross
1
Section Data File, Matrix E706 (IIB)
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applicationsand is the direct responsibility of Subcommittee
E2005 Guide for Benchmark Testing of Reactor Dosimetry
E10.05 on Nuclear Radiation Metrology. A brief overview of Guide E944 appears
in Standard and Reference Neutron Fields
in Master Matrix E706 in 5.3.1(IIA).
E2006 Guide for BenchmarkTesting of LightWater Reactor
Current edition approved Nov. 1, 2008. Published January 2009. Originally
approved in 1983. Last previous edition approved in 2002 as E944 – 02. DOI: Calculations
10.1520/E0944-08.
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
3
Standards volume information, refer to the standard’s Document Summary page on The last approved version of this historical standard is referenced on
the ASTM website. DOI: 10.1520/E0944-08. www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E944 − 08
4
2.2 Nuclear Regulatory Commission Documents: 3.2.4 The reaction cross sections of the dosimetry sensors
NUREG/CR-1861 PCA Experiments and Blind Test are obtained from an evaluated cross section file. The cross
NUREG/CR-2222 Theory and Practice of General Adjust- section
...

This document is not anASTM standard and is intended only to provide the user of anASTM 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:E 944–96 Designation:E944–08
Standard Guide for
Application of Neutron Spectrum Adjustment Methods in
1
Reactor Surveillance, E706 (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 (ϵ) 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:
E170170 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 byAnalysis of Molybdenum-99 Radioactivity fromFrom Fission Dosimeters
E393 Test Method for Measuring Reaction Rates by Analysis of Barium-140 fromFrom Fission Dosimeters
E481 Test Method for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver
,
2
E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E 706(IID) 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 LowAlloy Steels inTerms of Displacements PerAtom (DPA),
,
2 3
E 706(ID) 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
2
E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
(IIE)Benchmark Testing of Reactor Vessel Dosimetry
4
(IIID)Application andAnalysis of Damaged Monitors for Reactor Vessel Surveillance Master Matrix for Light-Water Reactor
Pressure Vessel Surveillance Standards, E 706(0)
2,3
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706(IIC) E 706 (IIC)
,
2 3
E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E 706(IA) E706(IA)
E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E
2,3
706(IIIB) E706(IIIB)
E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance,
2,3
E706(IIIC) E706 (IIIC)
1
This guide is under the jurisdiction of ASTM Committee E-10 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 E 706E706in 5.3.1(IIA).
Current edition approved July 10, 1996. Published August 1996. Originally published as E 944–83. Last previous edition E944–89.
Current edition approved Nov. 1, 2008. Published January 2009. Originally approved in 1983. Last previous edition approved in 2002 as E944 – 02. DOI:
10.1520/E0944-08.
2
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
, Vol 12.02.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 ----------------------
E944–08
2
E10051005 Test Metho
...

This document is not anASTM standard and is intended only to provide the user of anASTM 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:E944–02 Designation:E944–08
Standard Guide for
Application of Neutron Spectrum Adjustment Methods in
1
Reactor Surveillance, E706 (IIA)
This standard is issued under the fixed designation E 944; 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:
E 170 Terminology Relating to Radiation Measurements and Dosimetry
E 262 Test Method for Determining Thermal Neutron Reaction and Fluence Rates by Radioactivation Techniques
E 263 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron
E 264 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel
E 265 Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32
E 266 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum
E 343 Test Method for Measuring Reaction Rates byAnalysis of Molybdenum-99 Radioactivity fromFrom Fission Dosimeters
E 393 Test Method for Measuring Reaction Rates by Analysis of Barium-140 fromFrom Fission Dosimeters
E 481 Test Method for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver
2,
E 482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706(IID) E706 (IID)
E 523 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
E 526 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Titanium
E 693 PracticeforCharacterizingNeutronExposuresinIronandLowAlloySteelsinTermsofDisplacementsPerAtom(DPA),
2,3
E706(ID) E 706(ID)
E 704 Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
E 705 Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
E 706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E 706(0)
2,3
E 844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E706(IIC) E 706(IIC)
,
2 3
E 853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706(IA) E706(IA)
E 854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance,
,
2 3
E706(IIIB) E706(IIIB)
E 910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance,
,
2 3
E706(IIIC) E706 (IIIC)
2
E 1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E706(IIIA) E
706(IIIA)
,
2 3
E 1018 Guide for Application of ASTM Evaluated Cross Section Data File, E706(IIB) Matrix E 706 (IIB)
2
E 2005 Guide for the Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Field, E706 (IIE-I) Fields
1
ThisguideisunderthejurisdictionofASTMCommitteeE10onNuclearTechnologyandApplicationsandisthedirectresponsibilityofSubcommitteeE10.05onNuclear
Radiation Metrology. A brief overview of Guide E 944 appears in Master Matrix E 706 in 5.3.1(IIA).
Current edition approved June 10, 2002. Published September 2002. Originally published as E944–83. Last previous edition E944–96.
Current edition approved Nov. 1, 2008. Published January 2009. Originally approved in 1983. Last previous edition approved in 2002 as E 944 – 02.
2
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
, Vol 12.02.volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ------
...