ASTM E1035-18

Standard Practice for Determining Neutron Exposures for Nuclear Reactor<brk/> Vessel Support Structures

SIGNIFICANCE AND USE
3.1 Prediction of neutron radiation effects to pressure vessel steels has long been a part of the design and operation of light water reactor power plants. Both the federal regulatory agencies (see 2.3) and national standards groups (see 2.1 and 2.2) have promulgated regulations and standards to ensure safe operation of these vessels. The support structures for pressurized water reactor vessels may also be subject to similar neutron radiation effects (1, 3-6).6 The objective of this practice is to provide guidelines for determining the neutron radiation exposures experienced by individual vessel supports.  
3.2 It is known that high energy photons can also produce displacement damage effects that may be similar to those produced by neutrons. These effects are known to be much less at the belt line of a light water reactor pressure vessel than those induced by neutrons. The same has not been proven for all locations within vessel support structures. Therefore, it may be prudent to apply coupled neutron-photon transport methods and photon induced displacement cross sections to determine whether gamma-induced dpa exceeds the screening level of 3.0 × 10-4, used in this practice for neutron exposures. (See 1.3).
SCOPE
1.1 This practice covers procedures for monitoring the neutron radiation exposures experienced by ferritic materials in nuclear reactor vessel support structures located in the vicinity of the active core. This practice includes guidelines for:  
1.1.1 Selecting appropriate dosimetric sensor sets and their proper installation in reactor cavities.  
1.1.2 Making appropriate neutronics calculations to predict neutron radiation exposures.  
1.2 The values stated in SI units are to be regarded as standard; units that are not SI can be found in Terminology E170 and are to be regarded as standard. Any values in parentheses are for information only.  
1.3 This practice is applicable to all pressurized water reactors whose vessel supports will experience a lifetime neutron fluence (E > 1 MeV) that exceeds 1 × 1017 neutrons/cm 2 or exceeds 3.0 × 10−4 dpa.(1)2 (See Terminology E170.)  
1.4 Exposure of vessel support structures by gamma radiation is not included in the scope of this practice, but see the brief discussion of this issue in 3.2.  
1.5 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. (For example (2))  
1.6 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-May-2018
• ICS: 27.120.20 - Nuclear power plants. Safety
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.05 - Nuclear Radiation Metrology

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: E1035 − 18
Standard Practice for
Determining Neutron Exposures for Nuclear Reactor
1
Vessel Support Structures
This standard is issued under the fixed designation E1035; 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 2. Referenced Documents
3
2.1 ASTM Standards:
1.1 This practice covers procedures for monitoring the
E170 Terminology Relating to Radiation Measurements and
neutron radiation exposures experienced by ferritic materials in
Dosimetry
nuclear reactor vessel support structures located in the vicinity
E482 Guide for Application of Neutron Transport Methods
of the active core. This practice includes guidelines for:
for Reactor Vessel Surveillance
1.1.1 Selecting appropriate dosimetric sensor sets and their
E693 Practice for Characterizing Neutron Exposures in Iron
proper installation in reactor cavities.
and Low Alloy Steels in Terms of Displacements Per
1.1.2 Making appropriate neutronics calculations to predict
Atom (DPA)
neutron radiation exposures.
E844 Guide for Sensor Set Design and Irradiation for
1.2 The values stated in SI units are to be regarded as
Reactor Surveillance
standard; units that are not SI can be found in Terminology
E854 Test Method for Application and Analysis of Solid
E170 and are to be regarded as standard. Any values in
State Track Recorder (SSTR) Monitors for Reactor Sur-
parentheses are for information only.
veillance
1.3 This practice is applicable to all pressurized water E910 Test Method for Application and Analysis of Helium
reactors whose vessel supports will experience a lifetime
Accumulation Fluence Monitors for Reactor Vessel Sur-
17
neutron fluence (E > 1 MeV) that exceeds 1 × 10 neutrons/ veillance
2 −4 2
cm or exceeds 3.0 × 10 dpa.(1) (See Terminology E170.)
E944 Guide for Application of Neutron Spectrum Adjust-
ment Methods in Reactor Surveillance
1.4 Exposure of vessel support structures by gamma radia-
E1005 Test Method for Application and Analysis of Radio-
tion is not included in the scope of this practice, but see the
metric Monitors for Reactor Vessel Surveillance
brief discussion of this issue in 3.2.
E1018 Guide for Application of ASTM Evaluated Cross
1.5 This standard does not purport to address all of the
Section Data File
safety concerns, if any, associated with its use. It is the
E2956 Guide for Monitoring the Neutron Exposure of LWR
responsibility of the user of this standard to establish appro-
Reactor Pressure Vessels
priate safety, health, and environmental practices and deter-
2.2 ASME Standard:
mine the applicability of regulatory limitations prior to use. 4
Boiler and Pressure Vessel Code, Section III
(For example (2))
2.3 Nuclear Regulatory Documents:
1.6 This international standard was developed in accor-
Code of Federal Regulations, “Fracture Toughness
5
dance with internationally recognized principles on standard-
Requirements,” Chapter 10, Part 50, Appendix G
ization established in the Decision on Principles for the
Code of Federal Regulations, “Reactor Vessel Materials
Development of International Standards, Guides and Recom-
Surveillance Program Requirements,” Chapter 10, Part
5
mendations issued by the World Trade Organization Technical
50, Appendix H
Barriers to Trade (TBT) Committee.
Regulatory Guide 1.99, Rev. 2, “Effects of Residual Ele-
ments on Predicted Radiation Damage on Reactor Vessel
1 3
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Technology and Applicationsand is the direct responsibility of Subcommittee contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
E10.05 on Nuclear Radiation Metrology. Standards volume information, refer to the standard’s Document Summary page on
Current edition approved June 1, 2018. Published July 2018. Originally approved the ASTM website.
4
in 1985. Last previous edition approved in 2013 as E1035–13. DOI: 10.1520/ Available from American Society of Mechanical Engineers, 345 E. 47th St.,
E1035-18. New York, NY 10017.
2 5
The boldface numbers in parentheses refer to a list of references at the end of Available from Superintendent of Documents, U.S. Government Printing
this practice. Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E1035 − 18
Materials,” U. S. Nuclear Regulatory Commission, May 5. Determination of Neutron Exposure Parameter Values
5
1988
5.1 Neutronics Calculations—All ne
...

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.
Designation: E1035 − 13 E1035 − 18
Standard Practice for
Determining Neutron Exposures for Nuclear Reactor
1
Vessel Support Structures
This standard is issued under the fixed designation E1035; 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 practice covers procedures for monitoring the neutron radiation exposures experienced by ferritic materials in nuclear
reactor vessel support structures located in the vicinity of the active core. This practice includes guidelines for:
1.1.1 Selecting appropriate dosimetric sensor sets and their proper installation in reactor cavities.
1.1.2 Making appropriate neutronics calculations to predict neutron radiation exposures.
1.2 The values stated in SI units are to be regarded as standard; units that are not SI can be found in Terminology E170 and
are to be regarded as standard. Any values in parentheses are for information only.
1.3 This practice is applicable to all pressurized water reactors whose vessel supports will experience a lifetime neutron fluence
17 2 −4 2
(E > 1 MeV) that exceeds 1 × 10 neutrons/cm or exceeds 3.0 × 10 dpa.(1) (See Terminology E170.)
1.4 Exposure of vessel support structures by gamma radiation is not included in the scope of this practice, but see the brief
discussion of this issue in 3.2.
1.5 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 safety, health, and healthenvironmental practices and determine the
applicability of regulatory limitations prior to use. (For example (2))
1.6 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
3
2.1 ASTM Standards:
E170 Terminology Relating to Radiation Measurements and Dosimetry
E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
E693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance
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
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor 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
E2956 Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
2.2 ASME Standard:
4
Boiler and Pressure Vessel Code, Section III
1
This practice 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 Jan. 1, 2013June 1, 2018. Published January 2013July 2018. Originally approved in 1985. Last previous edition approved in 20082013 as
E1035–08.–13. DOI: 10.1520/E1035-13.10.1520/E1035-18.
2
Based on data from Table 5 of Master MatrixThe boldface numbers in parentheses refer to a list of references at E706 and Reference 5.the end of this practice.
3
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.
4
Available from American Society of Mechanical Engineers, 345 E. 47th St., New York, NY 10017.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E1035 − 18
2.3 Nuclear Regulatory Documents:
5
Code of Federal Regulations, “Fracture Toughness Requirements,” Chapter 10, Part 50, Appendix G
Code of Federal Regulations, “Reactor Vessel Materials Surveillance Program Requirements,” Ch
...