SAE AMS2515 Polytetrafluoroethylene (PTFE) Resin Coating, Low Build, 370 to 400 掳C (698 to 752 掳F) Fusion

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Product Code:SAE AMS2515
Title:Polytetrafluoroethylene (PTFE) Resin Coating, Low Build, 370 to 400 掳C (698 to 752 掳F) Fusion
Issuing Committee:Ams P Polymeric Materials Committee
Scope:This specification establishes the engineering requirements for producing thin coatings of polytetrafluoroethylene (PTFE) resin on parts and the properties of such coatings.
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【英文标准名称】:Glossaryoftermsforcargotyperearbodyofmotortrucks
【原文标准名称】:载货型卡车后车体术语汇编
【标准号】:JISD0105-1987
【标准状态】:现行
【国别】:日本
【发布日期】:1987-07-01
【实施或试行日期】:
【发布单位】:日本工业标准调查会(JP-JISC)
【起草单位】:TechnicalCommitteeonRoadVehicles
【标准类型】:()
【标准水平】:()
【中文主题词】:词汇;行李间;术语;道路车辆车身;工业用货车;运载工具主体制造
【英文主题词】:industrialtrucks;vehiclebodywork;roadvehiclebodies;terminology;vocabulary;luggagecompartments
【摘要】:この規格は,普通自動車のトラックの普通荷台及びその構造がそ標準的な荷台の部品に関する用語について規定する。注JISD0101(自動車の種類に関する用語)による。
【中国标准分类号】:T43
【国际标准分类号】:01_040_43;43_020
【页数】:20P;A4
【正文语种】:日语


【英文标准名称】:StandardGuideforIn-ServiceAnnealingofLight-WaterModeratedNuclearReactorVessels
【原文标准名称】:轻水冷却核反应堆容器在运转中逐渐冷却的标准指南
【标准号】:ASTME509-2003(2008)
【标准状态】:现行
【国别】:美国
【发布日期】:2003
【实施或试行日期】:
【发布单位】:美国材料与试验协会(US-ASTM)
【起草单位】:E10.02
【标准类型】:(Guide)
【标准水平】:()
【中文主题词】:
【英文主题词】:fracturetoughness;irradiation;nuclearreactorvessels(light-watermoderated);radiationexposure;surveillance(ofnuclearreactorvessels);Annealing;Fracturetesting--nuclearreactors;Nuclearapplications/materials--steel;Nuclearreactorvessels
【摘要】:Reactorvesselsmadeofferriticsteelsaredesignedwiththeexpectationofprogressivechangesinmaterialpropertiesresultingfromin-serviceneutronexposure.Intheoperationoflight-water-coolednuclearpowerreactors,changesinpressure-temperature(Px2013;T)limitsaremadeperiodicallyduringservicelifetoaccountfortheeffectsofneutronradiationontheductile-to-brittletransitiontemperaturematerialproperties.Ifthedegreeofneutronembrittlementbecomeslarge,therestrictionsonoperationduringnormalheat-upandcooldownmaybecomesevere.Additionalconsiderationshouldbegiventopostulatedevents,suchaspressurizedthermalshock(PTS).Areductionintheuppershelftoughnessalsooccursfromneutronexposure,andthisdecreasemayreducethemarginofsafetyagainstductilefracture.Whenitappearsthatthesesituationscoulddevelop,certainalternativesareavailablethatreducetheproblemorpostponethetimeatwhichplantrestrictionsmustbeconsidered.Oneofthesealternativesistothermallyannealthereactorvesselbeltlineregion,thatis,toheatthebeltlineregiontoatemperaturesufficientlyabovethenormaloperatingtemperaturetorecoverasignificantportionoftheoriginalfracturetoughnessandothermaterialpropertiesthatwerelostasaresultofneutronembrittlement.Preparationandplanningforanin-serviceannealshouldbeginearlysothatpertinentinformationcanbeobtainedtoguidetheannealingoperation.Sufficienttimeshouldbeallocatedtoevaluatetheexpectedbenefitsinoperatinglifetobegainedbyannealing;toevaluatetheannealingmethodtobeemployed;toperformthenecessarysystemstudiesandstressevaluations;toevaluatetheexpectedannealingrecoveryandreembrittlementbehavior;todevelopandfunctionallytestsuchequipmentasmayberequiredtodothein-serviceannealing;and,totrainpersonneltoperformtheanneal.Selectionoftheannealingtemperaturerequiresabalanceofopposingconditions.Higherannealingtemperatures,andlongerannealingtimes,canproducegreaterrecoveryoffracturetoughnessandothermaterialpropertiesandtherebyincreasethepost-anneallifetime.Theannealingtemperaturealsocanhaveanimpactonthereembrittlementtrendaftertheanneal.Ontheotherhand,highertemperaturescancreateotherundesirablepropertyeffectssuchaspermanentcreepdeformationortemperembrittlement.Thesehighertemperaturesalsocancauseengineeringdifficulties,thatis,coreandcoolantremovalandstorage,localizedheatingeffects,etc.,inpreventingtheannealingoperationfromdistortingthevesselordamagingvesselsupports,primarycoolantpiping,adjacentconcrete,insulation,etc.SeeASMECodeCaseN-557forfurtherguidanceonannealingconditionsandthermal-stressevaluations(2).Whenareactorvesselapproachesastateofembrittlementsuchthatannealingisconsidered,themajorcriterionisthenumberofyearsofadditionalservicelifethatannealingofthevesselwillprovide.Twopiecesofinformationareneededtoanswerthequestion:thepost-annealadjustedRTNDTanduppershelfenergylevel,andtheirsubsequentchangesduringfutureirradiation.Furthermore,ifavesselisannealed,thesameinformationisneededasthebasisforestablishingpressure-temperaturelimitsfortheperiodimmediatelyfollowingtheannealanddemonstratingcompliancewithotherdesignrequirementsandthePTSscreeningcriteria.Theeffectsonuppershelftoughnesssimilarlymustbeaddressed.ThisguideprimarilyaddressesRTNDTchanges.HandlingoftheuppershelfispossibleusingasimilarapproachasindicatedinNRCRegulatoryGuide1.16.......
【中国标准分类号】:F69
【国际标准分类号】:27_120_10
【页数】:11P.;A4
【正文语种】:英语