1、Designation:E103518Standard Practice forDetermining Neutron Exposures for Nuclear ReactorVessel Support Structures1This standard is issued under the fixed designation E1035;the number immediately following the designation indicates the year oforiginal adoption or,in the case of revision,the year of
2、last revision.A number in parentheses indicates the year of last reapproval.Asuperscript epsilon()indicates an editorial change since the last revision or reapproval.1.Scope1.1 This practice covers procedures for monitoring theneutron radiation exposures experienced by ferritic materials innuclear r
3、eactor vessel support structures located in the vicinityof the active core.This practice includes guidelines for:1.1.1 Selecting appropriate dosimetric sensor sets and theirproper installation in reactor cavities.1.1.2 Making appropriate neutronics calculations to predictneutron radiation exposures.
4、1.2 The values stated in SI units are to be regarded asstandard;units that are not SI can be found in TerminologyE170 and are to be regarded as standard.Any values inparentheses are for information only.1.3 This practice is applicable to all pressurized waterreactors whose vessel supports will exper
5、ience a lifetimeneutron fluence(E 1 MeV)that exceeds 1 1017neutrons/cm2or exceeds 3.0 104dpa.(1)2(See Terminology E170.)1.4 Exposure of vessel support structures by gamma radia-tion is not included in the scope of this practice,but see thebrief discussion of this issue in 3.2.1.5 This standard does
6、not purport to address all of thesafety concerns,if any,associated with its use.It is theresponsibility of the user of this standard to establish appro-priate safety,health,and environmental practices and deter-mine the applicability of regulatory limitations prior to use.(For example(2)1.6 This int
7、ernational standard was developed in accor-dance with internationally recognized principles on standard-ization established in the Decision on Principles for theDevelopment of International Standards,Guides and Recom-mendations issued by the World Trade Organization TechnicalBarriers to Trade(TBT)Co
8、mmittee.2.Referenced Documents2.1 ASTM Standards:3E170 Terminology Relating to Radiation Measurements andDosimetryE482 Guide for Application of Neutron Transport Methodsfor Reactor Vessel SurveillanceE693 Practice for Characterizing Neutron Exposures in Ironand Low Alloy Steels in Terms of Displacem
9、ents PerAtom(DPA)E844 Guide for Sensor Set Design and Irradiation forReactor SurveillanceE854 Test Method for Application and Analysis of SolidState Track Recorder(SSTR)Monitors for Reactor Sur-veillanceE910 Test Method for Application and Analysis of HeliumAccumulation Fluence Monitors for Reactor
10、Vessel Sur-veillanceE944 Guide for Application of Neutron Spectrum Adjust-ment Methods in Reactor SurveillanceE1005 Test Method for Application and Analysis of Radio-metric Monitors for Reactor Vessel SurveillanceE1018 Guide for Application of ASTM Evaluated CrossSection Data FileE2956 Guide for Mon
11、itoring the Neutron Exposure of LWRReactor Pressure Vessels2.2 ASME Standard:Boiler and Pressure Vessel Code,Section III42.3 Nuclear Regulatory Documents:CodeofFederalRegulations,“FractureToughnessRequirements,”Chapter 10,Part 50,Appendix G5Code of Federal Regulations,“Reactor Vessel MaterialsSurvei
12、llance Program Requirements,”Chapter 10,Part50,Appendix H5Regulatory Guide 1.99,Rev.2,“Effects of Residual Ele-ments on Predicted Radiation Damage on Reactor Vessel1This practice is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applicationsand is the direct responsibility of
13、SubcommitteeE10.05 on Nuclear Radiation Metrology.Current edition approved June 1,2018.Published July 2018.Originally approvedin 1985.Last previous edition approved in 2013 as E103513.DOI:10.1520/E1035-18.2The boldface numbers in parentheses refer to a list of references at the end ofthis practice.3
14、For referenced ASTM standards,visit the ASTM website,www.astm.org,orcontact ASTM Customer Service at serviceastm.org.For Annual Book of ASTMStandards volume information,refer to the standards Document Summary page onthe ASTM website.4Available from American Society of Mechanical Engineers,345 E.47th
15、 St.,New York,NY 10017.5Available from Superintendent of Documents,U.S.Government PrintingOffice,Washington,DC 20402.Copyright ASTM International,100 Barr Harbor Drive,PO Box C700,West Conshohocken,PA 19428-2959.United StatesThis international standard was developed in accordance with internationall
16、y recognized principles on standardization established in the Decision on Principles for theDevelopment of International Standards,Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade(TBT)Committee.1 Materials,”U.S.Nuclear Regulatory Commission,May198853.Significance and Use3.1 Prediction of neutron radiation effects to pressure vesselsteels has long been a part of the design and operation of lightwater reactor power plants.Both the federal regulatory age
