ASTM E185-2010 5000 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels《轻水中型核动力反应堆罐监测计划设计的标准实施规程》.pdf
《ASTM E185-2010 5000 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels《轻水中型核动力反应堆罐监测计划设计的标准实施规程》.pdf》由会员分享,可在线阅读,更多相关《ASTM E185-2010 5000 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels《轻水中型核动力反应堆罐监测计划设计的标准实施规程》.pdf(8页珍藏版)》请在麦多课文档分享上搜索。
1、Designation: E185 10Standard 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 revisio
2、n, 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 procedures for designing a surveil-lance program for monitoring the radiation-indu
3、ced changes inthe mechanical properties of ferritic materials in light-watermoderated nuclear power reactor vessels. This practice in-cludes the minimum requirements for the design of a surveil-lance program, selection of vessel material to be included, andthe initial schedule for evaluation of mate
4、rials.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) at the end oflicense (EOL) exceeds 1 3 1021neutrons/m2(1 3 1017n/cm2)at the inside surface of the reactor vessel.1.3 This practice applies
5、only to the planning and design ofsurveillance programs for reactor vessels designed and builtafter the effective date of this practice. Previous versions ofPractice E185 apply to earlier reactor vessels.1.4 This practice does not provide specific procedures formonitoring the radiation induced chang
6、es in properties beyondthe design life, but the procedure described may provideguidance for developing such a surveillance program.1.5 The values stated in SI units are to be regarded as thestandard. The values given in parentheses are for informationonly.NOTE 1The increased complexity of the requir
7、ements 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 a surveil-lance program. Practice E2215 describes the procedures for testing and
8、evaluation of surveillance capsules removed from a surveillance programas defined in the current or previous editions of Practice E185. GuideE636 provides guidance for conducting additional mechanical tests. Asummary of the many major revisions to Practice E185 since its originalissuance is containe
9、d in 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 MetallicMaterialsE21 Test Methods for
10、Elevated Temperature Tension Testsof Metallic MaterialsE23 Test Methods for Notched Bar Impact Testing ofMetallic MaterialsE170 Terminology Relating to Radiation Measurements andDosimetryE208 Test Method for Conducting Drop-Weight Test toDetermine Nil-Ductility Transition Temperature of FerriticStee
11、lsE482 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)E900 Guide for
12、 Predicting Radiation-Induced TransitionTemperature Shift in Reactor Vessel Materials, E706 (IIF)E1214 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 Fr
13、acture Tough-nessE1921 Test Method for Determination of Reference Tem-perature, To, for Ferritic Steels in the Transition RangeE2215 Practice for Evaluation of Surveillance Capsules1This practice is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applications and is the direct
14、responsibility of SubcommitteeE10.02 on Behavior and Use of Nuclear Structural Materials.Current edition approved March 1, 2010. Published April 2010. Originallyapproved in 1961 as E185 61 T. Last previous edition approved in 2002 asE185 02. DOI: 10.1520/E0185-10.2For referenced ASTM standards, visi
15、t 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.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-29
16、59, United States.from Light-Water Moderated Nuclear Power Reactor Ves-sels2.2 ASME Standards:3American Society of Mechanical Engineers, Boiler andPressure Vessel Code, Sections III and XIASME Boiler and Pressure Vessel Code Case N-629, Use ofFracture Toughness Test Data to Establish ReferenceTemper
17、ature for Pressure Retaining Materials, Section XI,Division 1ASME Boiler and Pressure Vessel Code Case N-631, Use ofFracture Toughness Test Data to Establish ReferenceTemperature for Pressure Retaining Materials Other ThanBolting for Class 1 Vessels, Section III, Division 13. Terminology3.1 Definiti
18、ons:3.1.1 base metalas-fabricated plate material or forgingmaterial other than a weld or its corresponding heat-affected-zone (HAZ).3.1.2 beltlinethe irradiated region of the reactor vessel(shell material including weld seams and plates or forgings)that directly surrounds the effective height of the
19、 active core.Note that materials in regions adjacent to the beltline maysustain sufficient neutron damage to warrant consideration inthe selection of surveillance materials.3.1.3 Charpy transition temperature curvea graphic orcurve-fitted presentation, or both, of absorbed energy, lateralexpansion,
20、and fracture appearance as functions of test tem-perature, extending over a range including the lower shelf (5 %or less shear fracture appearance), transition region, and theupper shelf (95 % or greater shear fracture appearance).3.1.4 Charpy transition temperature shiftthe difference inthe 40.7J (3
21、0 ft-lbf) index temperatures for the best fit(average) Charpy absorbed energy curve measured before andafter irradiation.3.1.5 Charpy upper-shelf energy levelthe average energyvalue for all Charpy specimen tests (preferably three or more)whose test temperature is at or above the Charpy upper-shelfon
22、set; specimens tested at temperatures greater than 83C(150F) above the Charpy upper-shelf onset shall not beincluded, unless no data are available between the onsettemperature and onset +83C (+150F).3.1.6 Charpy upper-shelf onsetthe test temperature abovewhich the fracture appearance of all Charpy s
23、pecimens testedis at or above 95 % shear.3.1.7 end-of-license (EOL)the design lifetime in terms ofyears corresponding to the operating license period.3.1.8 heat-affected-zone (HAZ)plate material or forgingmaterial extending outward from, but not including, the weldfusion line in which the microstruc
24、ture of the base metal hasbeen altered by the heat of the welding process.3.1.9 index temperaturethat temperature corresponding toa predetermined level of absorbed energy, lateral expansion, orfracture appearance obtained from the best-fit (average)Charpy transition curve.3.1.10 lead factorthe ratio
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