Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance

SIGNIFICANCE AND USE
4.1 In neutron dosimetry, a fission or non-fission dosimeter, or combination of dosimeters, can be used for determining a fluence rate, fluence, or neutron spectrum in nuclear reactors. Each dosimeter is sensitive to a specific energy range, and, if desired, increased accuracy in a fluence-rate spectrum can be achieved by the use of several dosimeters each covering specific neutron energy ranges.  
4.2 A wide variety of detector materials is used for various purposes. Many of these substances overlap in the energy of the neutrons which they will detect, but many different materials are used for a variety of reasons. These reasons include available analysis equipment, different cross sections for different fluence-rate levels and spectra, preferred chemical or physical properties, and, in the case of radiometric dosimeters, varying requirements for different half-life isotopes, possible interfering activities, and chemical separation requirements.
SCOPE
1.1 This guide covers the selection, design, irradiation, post-irradiation handling, and quality control of neutron dosimeters (sensors), thermal neutron shields, and capsules for reactor surveillance neutron dosimetry.  
1.2 The values stated in SI units are to be regarded as standard. Values in parentheses are for information only.  
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.

General Information

Status
Published
Publication Date
31-May-2018
Current Stage
Ref Project

Relations

Buy Standard

Guide
ASTM E844-18 - Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance
English language
8 pages
sale 15% off
Preview
sale 15% off
Preview
Guide
REDLINE ASTM E844-18 - Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance
English language
8 pages
sale 15% off
Preview
sale 15% off
Preview

Standards Content (Sample)

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: E844 − 18
Standard Guide for
1
Sensor Set Design and Irradiation for Reactor Surveillance
This standard is issued under the fixed designation E844; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope E1018Guide for Application of ASTM Evaluated Cross
Section Data File
1.1 This guide covers the selection, design, irradiation,
E1214Guide for Use of Melt Wire Temperature Monitors
post-irradiation handling, and quality control of neutron do-
for Reactor Vessel Surveillance
simeters (sensors), thermal neutron shields, and capsules for
E2005Guide for Benchmark Testing of Reactor Dosimetry
reactor surveillance neutron dosimetry.
in Standard and Reference Neutron Fields
1.2 The values stated in SI units are to be regarded as
E2006GuideforBenchmarkTestingofLightWaterReactor
standard. Values in parentheses are for information only.
Calculations
1.3 This standard does not purport to address all of the
E2956Guide for Monitoring the Neutron Exposure of LWR
safety concerns, if any, associated with its use. It is the Reactor Pressure Vessels
responsibility of the user of this standard to establish appro-
3. Terminology
priate safety, health, and environmental practices and deter-
mine the applicability of regulatory limitations prior to use.
3.1 Definitions:
1.4 This international standard was developed in accor-
3.1.1 neutron dosimeter, sensor, monitor—a substance irra-
dance with internationally recognized principles on standard-
diated in a neutron environment for the determination of
ization established in the Decision on Principles for the
neutron fluence rate, fluence, or spectrum, for example: radio-
Development of International Standards, Guides and Recom-
metricmonitor(RM),solidstatetrackrecorder(SSTR),helium
mendations issued by the World Trade Organization Technical
accumulation fluence monitor (HAFM), damage monitor
Barriers to Trade (TBT) Committee.
(DM), temperature monitor (TM).
3.1.2 thermal neutron shield—a substance (that is,
2. Referenced Documents
cadmium, boron, gadolinium) that filters or absorbs thermal
2
2.1 ASTM Standards:
neutrons.
E170Terminology Relating to Radiation Measurements and
3.2 For definitions or other terms used in this guide, refer to
Dosimetry
Terminology E170.
E261Practice for Determining Neutron Fluence, Fluence
Rate, and Spectra by Radioactivation Techniques
4. Significance and Use
E854Test Method for Application and Analysis of Solid
4.1 In neutron dosimetry, a fission or non-fission dosimeter,
State Track Recorder (SSTR) Monitors for Reactor Sur-
or combination of dosimeters, can be used for determining a
veillance
fluence rate, fluence, or neutron spectrum in nuclear reactors.
E910Test Method for Application and Analysis of Helium
Each dosimeter is sensitive to a specific energy range, and, if
Accumulation Fluence Monitors for Reactor Vessel Sur-
desired, increased accuracy in a fluence-rate spectrum can be
veillance
achieved by the use of several dosimeters each covering
E1005Test Method for Application and Analysis of Radio-
specific neutron energy ranges.
metric Monitors for Reactor Vessel Surveillance
4.2 Awide variety of detector materials is used for various
purposes. Many of these substances overlap in the energy of
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
the neutrons which they will detect, but many different
Technology and Applicationsand is the direct responsibility of Subcommittee
materials are used for a variety of reasons. These reasons
E10.05 on Nuclear Radiation Metrology.
include available analysis equipment, different cross sections
CurrenteditionapprovedJune1,2018.PublishedJuly2018.Originallyapproved
ɛ2
fordifferentfluence-ratelevelsandspectra,preferredchemical
in 1981. Last previous edition approved in 2014 as E844–09(2014) . DOI:
10.1520/E0844-18.
or physical properties, and, in the case of radiometric
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
dosimeters, varying requirements for different half-life
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
isotopes, possible interfering activities, and chemical separa-
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. tion requirements.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E844 − 1
...

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.
´2
Designation: E844 − 09 (Reapproved 2014) E844 − 18
Standard Guide for
1
Sensor Set Design and Irradiation for Reactor Surveillance
This standard is issued under the fixed designation E844; 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—Figures 1 and 2 were updated and editorial changes were made in September 2014.
2
ε NOTE—The title and Referenced Documents were udpated in May 2017.
1. Scope
1.1 This guide covers the selection, design, irradiation, post-irradiation handling, and quality control of neutron dosimeters
(sensors), thermal neutron shields, and capsules for reactor surveillance neutron dosimetry.
1.2 The values stated in SI units are to be regarded as standard. Values in parentheses are for information only.
1.3 This standard does not purport to address all of the safety problems,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
E261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
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
E1018 Guide for Application of ASTM Evaluated Cross Section Data File
E1214 Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
E2005 Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
E2006 Guide for Benchmark Testing of Light Water Reactor Calculations
E2956 Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
3. Terminology
3.1 Definitions:
3.1.1 neutron dosimeter, sensor, monitor—a substance irradiated in a neutron environment for the determination of neutron
fluence rate, fluence, or spectrum, for example: radiometric monitor (RM), solid state track recorder (SSTR), helium accumulation
fluence monitor (HAFM), damage monitor (DM), temperature monitor (TM).
3.1.2 thermal neutron shield—a substance (that is, cadmium, boron, gadolinium) that filters or absorbs thermal neutrons.
3.2 For definitions or other terms used in this guide, refer to Terminology E170.
4. Significance and Use
4.1 In neutron dosimetry, a fission or non-fission dosimeter, or combination of dosimeters, can be used for determining a fluence
rate, fluence, or neutron spectrum in nuclear reactors. Each dosimeter is sensitive to a specific energy range, and, if desired,
increased accuracy in a fluence-rate spectrum can be achieved by the use of several dosimeters each covering specific neutron
energy ranges.
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.
Current edition approved June 1, 2014June 1, 2018. Published July 2014July 2018. Originally approved in 1981. Last previous edition approved in 20092014 as
ɛ2
E844 – 09.E844 – 09(2014) . DOI: 10.1520/E0844-09R14E02.10.1520/E0844-18.
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.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E844 − 18
4.2 A wide variety of detector materials is used for various purposes. Many of these substances overlap in the energy of the
neutrons which
...

Questions, Comments and Discussion

Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.