ASTM_E_1006_-_13.pdf

Designation:E100613Standard Practice forAnalysis and Interpretation of Physics Dosimetry Resultsfrom Test Reactor Experiments1This standard is issued under the fixed designation E1006;the number immediately following the designation indicates the year oforiginal adoption or,in the case of revision,the year of 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 the methodology summarized inAnnex A1 to be used in the analysis and interpretation ofphysics-dosimetry results from test reactors.1.2 This practice relies on,and ties together,the applicationof several supporting ASTM standard practices,guides,andmethods.1.3 Support subject areas that are discussed include reactorphysics calculations,dosimeter selection and analysis,expo-sure units,and neutron spectrum adjustment methods.1.4 This practice is directed towards the development andapplication of physics-dosimetry-metallurgical data obtainedfrom test reactor irradiation experiments that are performed insupport of the operation,licensing,and regulation of LWRnuclear power plants.It specifically addresses the physics-dosimetry aspects of the problem.Procedures related to theanalysis,interpretation,and application of both test and powerreactor physics-dosimetry-metallurgy results are addressed inPractices E185,E853,and E1035,Guides E900,E2005,E2006and Test Method E646.1.5 This standard may involve hazardous materials,operations,and equipment.This standard does not purport toaddress all of the safety concerns,if any,associated with itsuse.It is the responsibility of the user of this standard toestablish appropriate safety and health practices and deter-mine the applicability of regulatory limitations prior to use.2.Referenced Documents2.1 ASTM Standards:2E185 Practice for Design of Surveillance Programs forLight-Water Moderated Nuclear Power Reactor VesselsE482 Guide for Application of Neutron Transport Methodsfor Reactor Vessel Surveillance,E706(IID)E646 Test Method for Tensile Strain-Hardening Exponents(n-Values)of Metallic Sheet MaterialsE693 Practice for Characterizing Neutron Exposures in Ironand Low Alloy Steels in Terms of Displacements PerAtom(DPA),E 706(ID)E706 Master Matrix for Light-Water Reactor Pressure VesselSurveillance Standards,E 706(0)(Withdrawn 2011)3E844 Guide for Sensor Set Design and Irradiation forReactor Surveillance,E 706(IIC)E853 Practice forAnalysis and Interpretation of Light-WaterReactor Surveillance Results,E706(IA)E854 Test Method for Application and Analysis of SolidState Track Recorder(SSTR)Monitors for ReactorSurveillance,E706(IIIB)E900 Guide for Predicting Radiation-Induced TransitionTemperature Shift in Reactor Vessel Materials,E706(IIF)E910 Test Method for Application and Analysis of HeliumAccumulation Fluence Monitors for Reactor VesselSurveillance,E706(IIIC)E944 Guide for Application of Neutron Spectrum Adjust-ment Methods in Reactor Surveillance,E 706(IIA)E1005 Test Method for Application and Analysis of Radio-metric Monitors for Reactor Vessel Surveillance,E 706(IIIA)E1018 Guide for Application of ASTM Evaluated CrossSection Data File,Matrix E706(IIB)E1035 Practice for Determining Neutron Exposures forNuclear Reactor Vessel Support StructuresE2005 Guide for Benchmark Testing of Reactor Dosimetryin Standard and Reference Neutron FieldsE2006 Guide for Benchmark Testing of Light Water ReactorCalculations2.2 Nuclear Regulatory Documents:CodeofFederalRegulations,“FractureToughnessRequirements,”Chapter 10,Part 50,Appendix G4Code of Federal Regulations,“Reactor Vessel MaterialsSurveillance Program Requirements,”Chapter 10,Part50,Appendix H41This practice is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applications and is the direct responsibility of SubcommitteeE10.05 on Nuclear Radiation Metrology.Current edition approved June 1,2013.Published July 2013.Originally approvedin 1984.Last previous edition approved in 2008 as E1006 08.DOI:10.1520/E1006-13.2The reference in parentheses refers to Section 5 as well as to Figs.1 and 2 ofMatrix E706.3The last approved version of this historical standard is referenced onwww.astm.org.4Available 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 States1 Regulatory Guide 1.99,Rev 2,“Radiation Embrittlement ofReactor Vessel Materials,”U.S.Nuclear RegulatoryCommission,May 198843.Significance and Use3.1 The mechanical properties of steels and other metals arealtered by exposure to neutron radiation.These propertychanges are assumed to be a function of chemical composition,metallurgical condition,temperature,fluence(perhaps alsofluence rate),and neutron spectrum.The influence of thesevariables is not completely understood.The functional depen-dency between property changes and neutron radiatio