ASTM_E_185_-_15e1.pdf

Designation:E185151Standard Practice forDesign of Surveillance Programs for Light-Water ModeratedNuclear Power Reactor Vessels1This standard is issued under the fixed designation E185;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.1NOTEParagraph X1.8 was corrected editorially in October 2015.1.Scope1.1 This practice covers procedures for designing a surveil-lance program for monitoring the radiation-induced changes inthe mechanical properties of ferritic materials in light-watermoderated nuclear power reactor vessels.New advanced light-water small modular reactor designs with a nominal designoutput of 300 MWe or less have not been specifically consid-ered in this practice.This practice includes the minimumrequirements for the design of a surveillance program,selec-tion of vessel material to be included,and the initial schedulefor evaluation of materials.1.2 This practice was developed for all light-water moder-ated nuclear power reactor vessels for which the predictedmaximum fast neutron fluence(E 1 MeV)exceeds 1 1021neutrons/m2(1 1017n/cm2)at the inside surface of the ferriticsteel reactor vessel.1.3 This practice does not provide specific procedures formonitoring the radiation induced changes in properties beyondthe design life.Practice E2215 addresses changes to thewithdrawal schedule during and beyond the design life.1.4 The values stated in SI units are to be regarded as thestandard.The values given in parentheses are for informationonly.NOTE1The increased complexity of the requirements for a light-water moderated nuclear power reactor vessel surveillance program hasnecessitated the separation of the requirements into three related stan-dards.Practice E185 describes the minimum requirements for design of asurveillance program.Practice E2215 describes the procedures for testingand evaluation of surveillance capsules removed from a reactor vessel.Guide E636 provides guidance for conducting additional mechanical tests.Asummary of the many major revisions to Practice E185 since its originalissuance is contained in Appendix X1.NOTE2This practice applies only to the planning and design ofsurveillance programs for reactor vessels designed and built after theeffective date of this practice.Previous versions of Practice E185 apply toearlier reactor vessels.See Appendix X1.2.Referenced Documents2.1 ASTM Standards:2A370 Test Methods and Definitions for Mechanical Testingof Steel ProductsA751 Test Methods,Practices,and Terminology for Chemi-cal Analysis of Steel ProductsE8/E8M Test Methods for Tension Testing of Metallic Ma-terialsE21 Test Methods for Elevated Temperature Tension Tests ofMetallic MaterialsE23 Test Methods for Notched Bar Impact Testing of Me-tallic MaterialsE170 Terminology Relating to Radiation Measurements andDosimetryE208 Test Method for Conducting Drop-Weight Test toDetermine Nil-Ductility Transition Temperature of Fer-ritic SteelsE482 Guide for Application of Neutron Transport Methodsfor Reactor Vessel Surveillance,E706(IID)E636 Guide for Conducting Supplemental SurveillanceTests for Nuclear Power Reactor Vessels,E 706(IH)E844 Guide for Sensor Set Design and Irradiation forReactor Surveillance,E 706(IIC)E853 Practice forAnalysis and Interpretation of Light-WaterReactor Surveillance ResultsE900 Guide for Predicting Radiation-Induced TransitionTemperature Shift in Reactor Vessel MaterialsE1214 Guide for Use of Melt Wire Temperature Monitorsfor Reactor Vessel Surveillance,E 706(IIIE)E1253 Guide for Reconstitution of Irradiated Charpy-SizedSpecimensE1820 Test Method for Measurement of Fracture ToughnessE1921 Test Method for Determination of ReferenceTemperature,To,for Ferritic Steels in the TransitionRange1This practice is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applications and is the direct responsibility of SubcommitteeE10.02 on Behavior and Use of Nuclear Structural Materials.Current edition approved June 1,2015.Published July 2015.Originally approvedin 1961 as E185 61 T.Last previous edition approved in 2010 as E185 10.DOI:10.1520/E0185-15E01.2For 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.Copyright ASTM International,100 Barr Harbor Drive,PO Box C700,West Conshohocken,PA 19428-2959.United States1 E2215 Practice for Evaluation of Surveillance Capsulesfrom Light-Water Moderated Nuclear Power Reactor Ves-selsE2298 Test Method for Instrumented Impact Testing ofMetallic MaterialsE2956 Guide for Monitoring the Neutron Exposure of LWRReactor Pressure Vessels2.2 ASME Standards:3Boiler and Pressure Vessel Code,Section III SubsectionNB-2000Boiler