ASTM E944-02

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

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: 09-Jun-2002
• 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 E944-96 - Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, (IIA)
• Effective Date: 10-Jun-2002
• Replaced By: ASTM E944-08 - Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E706 (IIA)
• Effective Date: 01-Nov-2008
• Referred By: ASTM E704-19 - Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
• Effective Date: 10-Jun-2002
• 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: 10-Jun-2002
• Referred By: ASTM E2956-23 - Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
• Effective Date: 10-Jun-2002
• Referred By: ASTM E900-21 - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
• Effective Date: 10-Jun-2002
• Referred By: ASTM E393-19 - Standard Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters
• Effective Date: 10-Jun-2002
• Referred By: ASTM E523-21e1 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
• Effective Date: 10-Jun-2002
• Referred By: ASTM E2059-20 - Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry
• Effective Date: 10-Jun-2002
• Referred By: ASTM E721-22 - Standard Guide for Determining Neutron Energy Spectra from Neutron Sensors for Radiation-Hardness Testing of Electronics
• Effective Date: 10-Jun-2002
• Referred By: ASTM E1035-18(2023) - Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
• Effective Date: 10-Jun-2002
• Referred By: ASTM E1297-18 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
• Effective Date: 10-Jun-2002
• Referred By: ASTM E1005-21 - Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
• Effective Date: 10-Jun-2002
• Referred By: ASTM E705-18 - Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
• Effective Date: 10-Jun-2002
• Referred By: ASTM E1006-21 - Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
• Effective Date: 10-Jun-2002

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:E944–02
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 (e) indicates an editorial change since the last revision or reapproval.
2
1. Scope Radioactivation of Cobalt and Silver
E 482 Guide forApplication of Neutron Transport Methods
1.1 This guide covers the analysis and interpretation of the
2,3
for Reactor Vessel Surveillance, E 706(IID)
physics dosimetry for LightWater Reactor (LWR) surveillance
E 523 Test Method for Measuring Fast-Neutron Reaction
programs. The main purpose is the application of adjustment
2
Rates by Radioactivation of Copper
methods to determine best estimates of neutron damage expo-
E 526 Test Method for Measuring Fast-Neutron Reaction
sure parameters and their uncertainties.
2
Rates by Radioactivation of Titanium
1.2 This guide is also applicable to irradiation damage
E 693 Practice for Characterizing Neutron Exposures in
studies in research reactors.
Iron and Low Alloy Steels in Terms of Displacements Per
1.3 This standard does not purport to address all of the
,
2 3
Atom (DPA), E 706(ID)
safety concerns, if any, associated with its use. It is the
E 704 Test Method for Measuring Reaction Rates by Ra-
responsibility of the user of this standard to establish appro-
2
dioactivation of Uranium-238
priate safety and health practices and determine the applica-
E 705 Test Method for Measuring Reaction Rates by Ra-
bility of regulatory limitations prior to use.
2
dioactivation of Neptunium-237
2. Referenced Documents
E 706 Master Matrix for Light-Water Reactor Pressure
2
Vessel Surveillance Standards
2.1 ASTM Standards:
E 844 Guide for Sensor Set Design and Irradiation for
E 170 Terminology Relating to Radiation Measurements
2,3
2
Reactor Surveillance, E 706(IIC)
and Dosimetry
E 853 Practice for Analysis and Interpretation of Light-
E 262 Test Method for Determining Thermal Neutron Re-
2,3
2
Water Reactor Surveillance Results, E 706(IA)
action and Fluence Rates by Radioactivation Techniques
E 854 Test Method for Application and Analysis of Solid
E 263 Test Method for Measuring Fast-Neutron Reaction
2
State Track Recorder (SSTR) Monitors for Reactor Sur-
Rates by Radioactivation of Iron
,
2 3
veillance, E 706(IIIB)
E 264 Test Method for Measuring Fast-Neutron Reaction
2
E 910 Test Method forApplication andAnalysis of Helium
Rates by Radioactivation of Nickel
Accumulation Fluence Monitors for Reactor Vessel Sur-
E 265 Test Method for Measuring Reaction Rates and
2,3
2
veillance, E706(IIIC)
Fast-Neutron Fluences by Radioactivation of Sulfur-32
E 1005 Test Method forApplication andAnalysis of Radio-
E 266 Test Method for Measuring Fast-Neutron Reaction
2
metric Monitors for Reactor Vessel Surveillance,
Rates by Radioactivation of Aluminum
2
E 706(IIIA)
E 343 TestMethodforMeasuringReactionRatesbyAnaly-
E 1018 Guide for Application of ASTM Evaluated Cross
sis of Molybdenum-99 Radioactivity from Fission Dosim-
,
2 3
2
Section Data File, E706(IIB)
eters
E 2005 Guide for the Benchmark Testing of Reactor Do-
E 393 TestMethodforMeasuringReactionRatesbyAnaly-
2
simetry in Standard and Reference Neutron Field, E706
sis of Barium-140 from Fission Dosimeters
2
(IIE-I)
E 481 Test Method for Measuring Neutron Fluence Rate by
E 2006 Guide for the Benchmark Testing of LWR Calcula-
,
2 3
tions E706 (IIE-2)
4
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear 2.2 Nuclear Regulatory Commission Documents:
Technology and Applicationsand is the direct responsibility of Subcommittee
E10.05onNuclearRadiationMetrology.AbriefoverviewofGuideE 944appearsin
3
Master Matrix E 706 in 5.3.1(IIA). The unnumbered references in parentheses refer to Section 5 as well as Figs. 1
Current edition approved June 10, 2002. Published September 2002. Originally
and 2 of Matrix E 706.
4
published as E 944 – 83. Last previous edition E944 – 96. Available from Superintendents of Documents, U. S. Government Printing
2
Annual Book of ASTM Standards, Vol 12.02. Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

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E944–02
NUREG/CR-1861 PCA Experiments and Blind Test s ~E!,i 5 1,2, . (3)
i
NUREG/CR-2222 Theory and Practice of General Adjust-
Used in connection with the group fluences, Eq 2, are the
ment and Model Fitting Procedures
calculated group-averaged cross sections s . These values are
ij
NUREG/CR-3318 LWR Pressure Vessel Surveillance Do-
defined throug
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