ASTM E2005-10

Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields

SIGNIFICANCE AND USE
This guide describes approaches for using neutron fields with well known characteristics to perform calibrations of neutron sensors, to intercompare different methods of dosimetry, and to corroborate procedures used to derive neutron field information from measurements of neutron sensor response.
This guide discusses only selected standard and reference neutron fields which are appropriate for benchmark testing of light-water reactor dosimetry. The Standard Fields considered are neutron source environments that closely approximate the unscattered neutron spectra from  252Cf spontaneous fission and  235U thermal neutron induced fission. These standard fields were chosen for their spectral similarity to the high energy region (E > 2 MeV) of reactor spectra. The various categories of benchmark fields are defined in Terminology E170.
There are other well known neutron fields that have been designed to mockup special environments, such as pressure vessel mockups in which it is possible to make dosimetry measurements inside of the steel volume of the “vessel.” When such mockups are suitably characterized they are also referred to as benchmark fields. A variety of these engineering benchmark fields have been developed, or pressed into service, to improve the accuracy of neutron dosimetry measurement techniques. These special benchmark experiments are discussed in Guide E2006, and in Refs (1) and (2).
SCOPE
1.1 This guide covers facilities and procedures for benchmarking neutron measurements and calculations. Particular sections of the guide discuss: the use of well-characterized benchmark neutron fields to calibrate integral neutron sensors; the use of certified-neutron-fluence standards to calibrate radiometric counting equipment or to determine interlaboratory measurement consistency; development of special benchmark fields to test neutron transport calculations; use of well-known fission spectra to benchmark spectrum-averaged cross sections; and the use of benchmarked data and calculations to determine the uncertainties in derived neutron dosimetry results.
1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

General Information

• Status: Historical
• Publication Date: 31-May-2010
• ICS: 27.120.10 - Reactor engineering
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.05 - Nuclear Radiation Metrology

Relations

• Replaces: ASTM E2005-05e1 - Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
• Effective Date: 01-Jun-2010
• 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-Jun-2010
• Referred By: ASTM E944-19 - Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
• Effective Date: 01-Jun-2010
• Referred By: ASTM E1854-19 - Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts
• Effective Date: 01-Jun-2010
• Referred By: ASTM E2006-22 - Standard Guide for Benchmark Testing of Light Water Reactor Calculations
• Effective Date: 01-Jun-2010
• Referred By: ASTM E910-18 - Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance
• Effective Date: 01-Jun-2010
• Referred By: ASTM E1006-21 - Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
• Effective Date: 01-Jun-2010
• Referred By: ASTM D1879-06(2023) - Standard Practice for Exposure of Adhesive Specimens to Ionizing Radiation
• Effective Date: 01-Jun-2010
• Referred By: ASTM E2956-23 - Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
• Effective Date: 01-Jun-2010
• Referred By: ASTM E1005-21 - Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
• Effective Date: 01-Jun-2010
• Referred By: ASTM E844-18 - Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance
• Effective Date: 01-Jun-2010
• Referred By: ASTM E1018-20e1 - Standard Guide for Application of ASTM Evaluated Cross Section Data File
• Effective Date: 01-Jun-2010
• Referred By: ASTM E261-16(2021) - Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
• Effective Date: 01-Jun-2010

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: E2005 − 10
StandardGuide for
Benchmark Testing of Reactor Dosimetry in Standard and
1
Reference Neutron Fields
This standard is issued under the fixed designation E2005; 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 facilities and procedures for bench-
sis of Barium-140 From Fission Dosimeters
marking neutron measurements and calculations. Particular
E482 Guide for Application of Neutron Transport Methods
sections of the guide discuss: the use of well-characterized
for Reactor Vessel Surveillance, E706 (IID)
benchmark neutron fields to calibrate integral neutron sensors;
E523 Test Method for Measuring Fast-Neutron Reaction
the use of certified-neutron-fluence standards to calibrate
Rates by Radioactivation of Copper
radiometriccountingequipmentortodetermineinterlaboratory
E526 Test Method for Measuring Fast-Neutron Reaction
measurement consistency; development of special benchmark
Rates by Radioactivation of Titanium
fields to test neutron transport calculations; use of well-known
E704 Test Method for Measuring Reaction Rates by Radio-
fissionspectratobenchmarkspectrum-averagedcrosssections;
activation of Uranium-238
and the use of benchmarked data and calculations to determine
E705 Test Method for Measuring Reaction Rates by Radio-
the uncertainties in derived neutron dosimetry results.
activation of Neptunium-237
1.2 The values stated in SI units are to be regarded as
E854 Test Method for Application and Analysis of Solid
standard. No other units of measurement are included in this
State Track Recorder (SSTR) Monitors for Reactor
standard.
Surveillance, E706(IIIB)
E910 Test Method for Application and Analysis of Helium
2. Referenced Documents
Accumulation Fluence Monitors for Reactor Vessel
2
2.1 ASTM Standards:
Surveillance, E706 (IIIC)
E170 Terminology Relating to Radiation Measurements and
E1297 Test Method for Measuring Fast-Neutron Reaction
Dosimetry
Rates by Radioactivation of Niobium
E261 Practice for Determining Neutron Fluence, Fluence
E2006 Guide for Benchmark Testing of Light Water Reactor
Rate, and Spectra by Radioactivation Techniques Calculations
E263 Test Method for Measuring Fast-Neutron Reaction
Rates by Radioactivation of Iron
3. Significance and Use
E264 Test Method for Measuring Fast-Neutron Reaction
3.1 This guide describes approaches for using neutron fields
Rates by Radioactivation of Nickel
with well known characteristics to perform calibrations of
E265 Test Method for Measuring Reaction Rates and Fast-
neutron sensors, to intercompare different methods of
Neutron Fluences by Radioactivation of Sulfur-32
dosimetry, and to corroborate procedures used to derive neu-
E266 Test Method for Measuring Fast-Neutron Reaction
tron field information from measurements of neutron sensor
Rates by Radioactivation of Aluminum
response.
E343 Test Method for Measuring Reaction Rates by Analy-
3.2 This guide discusses only selected standard and refer-
sis of Molybdenum-99 Radioactivity From Fission Do-
ence neutron fields which are appropriate for benchmark
testing of light-water reactor dosimetry. The Standard Fields
1
considered are neutron source environments that closely ap-
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
252
Technology and Applications and is the direct responsibility of Subcommittee
proximate the unscattered neutron spectra from Cf sponta-
E10.05 on Nuclear Radiation Metrology. 235
neous fission and U thermal neutron induced fission. These
Current edition approved June 1, 2010. Published August 2010. Originally
ϵ1 standard fields were chosen for their spectral similarity to the
approved in 1999. Last previous edition approved in 2005 as E2005 - 05 . DOI:
10.1520/E2005-10.
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. www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E2005 − 10
252
highenergyregion(E>2MeV)ofreactorspectra.Thevarious ated uncertainties for the NIST Cf irradiation facility are
categories of benchmark fields are defined in Terminology discussed in Ref (4). The principal uncertainties, which only
E170. total about 2.
...

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.
´1
Designation:E2005–05 Designation:E2005–10
Standard Guide for
Benchmark Testing of Reactor Dosimetry in Standard and
1
Reference Neutron Fields
This standard is issued under the fixed designation E2005; 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
´ NOTE—Editorial changes were made in June 2005.
1. Scope
1.1 This guide covers facilities and procedures for benchmarking neutron measurements and calculations. Particular sections of
the guide discuss: the use of well-characterized benchmark neutron fields to calibrate integral neutron sensors; the use of
certified-neutron-fluence standards to calibrate radiometric counting equipment or to determine interlaboratory measurement
consistency; development of special benchmark fields to test neutron transport calculations; use of well-known fission spectra to
benchmark spectrum-averaged cross sections; and the use of benchmarked data and calculations to determine the uncertainties in
derived neutron dosimetry results.
1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
2. Referenced Documents
2
2.1 ASTM Standards:
E170 Terminology Relating to Radiation Measurements and Dosimetry
E261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra 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
E393 Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters
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
E704 Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
E705 Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance,
E706(IIIB)
E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance,
E706 (IIIC)
E1297 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
E2006 Guide for Benchmark Testing of Light Water Reactor Calculations
3. Significance and Use
3.1 This guide describes approaches for using neutron fields with well known characteristics to perform calibrations of neutron
sensors, to intercompare different methods of dosimetry, and to corroborate procedures used to derive neutron field information
from measurements of neutron sensor response.
1
ThisguideisunderthejurisdictionofASTMCommitteeE10onNuclearTechnologyandApplicationsandisthedirectresponsibilityofSubcommitteeE10.05onNuclear
Radiation Metrology .
Current edition approved Jan. 1, 2005. Published February 2005. Originally approved in 1999. Last previous edition approved in 1999 as E2005-99. DOI:
10.1520/E2005-05E01.on Nuclear Radiation Metrology.
´1
Current edition approved June 1, 2010. Published August 2010. Originally approved in 1999. Last previous edition approved in 2005 as E2005 - 05 . DOI:
10.1520/E2005-10.
2
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM 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.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
E2005–10
3.2 This guide discusses only selected standard and reference neutron fields which are appropriate for benchmark testing of
light-water reactor dosimetry. The Standard Fields considered are neutron source environments that closely approximate the
252 235
unscatt
...