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

25、 of the peak neutron fluence(E 1 MeV) of the specimens in a surveillance capsule to thepeak neutron fluence (E 1 MeV) at the reactor pressure vesselinside surface.NOTE 2Changes in the reactor operating parameters and fuel man-agement may cause the lead factor to change.3.1.11 limiting materialsthe w

26、eld and base material withthe highest predicted transition temperature at EOL determinedby adding the appropriate transition temperature shift to theunirradiated RTNDT. The reference temperature shift can bedetermined from the relationship found in Guide E900. Thebasis for selecting the limiting mat

27、erial shall be documented.3.1.12 reference materialany steel that has been charac-terized as to the sensitivity of its tensile, impact and fracturetoughness properties to neutron radiation embrittlement.3.1.13 reference temperature (RTNDT)see subarticle NB-2300 of the ASME Boiler and Pressure Vessel

28、 Code, SectionIII, “Nuclear Power Plant Components” for the definition ofRTNDTfor unirradiated material based on Charpy (Test MethodE23) and drop weight tests (Test Method E208). ASME CodeCases N-629 and N-631 provide an alternative definition forthe reference temperature (RTTo) based on fracture to

29、ughnessproperties (Test Method E1921)3.1.14 standby capsulea surveillance capsule meeting therecommendations of this practice that is in the reactor vesselirradiation location, but whose withdrawal is not required bythis practice.3.2 Neutron Exposure Terminology:3.2.1 Definitions of terms related to

30、 neutron dosimetry andexposure are provided in Terminology E170.4. Significance and Use4.1 Predictions of neutron radiation effects on pressurevessel steels are considered in the design of light-watermoderated nuclear power reactors. Changes in system operat-ing parameters often are made throughout

31、the service life of thereactor vessel to account for radiation effects. Due to thevariability in the behavior of reactor vessel steels, a surveil-lance program is warranted to monitor changes in the proper-ties of actual vessel materials caused by long-term exposure tothe neutron radiation and tempe

32、rature environment of thereactor vessel. This practice describes the criteria that shouldbe considered in planning and implementing surveillance testprograms and points out precautions that should be taken toensure that: (1) capsule exposures can be related to beltlineexposures, (2) materials select

33、ed for the surveillance programare samples of those materials most likely to limit the operationof the reactor vessel, and (3) the test specimen types areappropriate for the evaluation of radiation effects on the reactorvessel.4.2 The methodology to be used in estimation of neutronexposure obtained

34、for reactor vessel surveillance programs isdefined in Guide E482.4.3 The design of a surveillance program for a given reactorvessel must consider the existing body of data on similarmaterials in addition to the specific materials used for thatreactor vessel. The amount of such data and the similarit

35、y of3Available from the American Society of Mechanical Engineers, Third ParkAvenue, New York, NY 10016.E185 102exposure conditions and material characteristics will determinetheir applicability for predicting radiation effects.5. Surveillance Program Design5.1 This section describes the minimum requ

36、irements forthe design of a surveillance program for monitoring theradiation-induced changes in the mechanical properties offerritic materials in the reactor vessel.5.2 Test Materials:5.2.1 Materials SelectionThe surveillance test materialsshall include, at minimum, the limiting base metal heat and

37、thelimiting weld. If a limiting material is outside the beltline, thelimiting beltline base and weld materials shall also be included.NOTE 3The predicted limiting material may change during operation.Therefore, it is prudent to include additional potentially limiting beltlinematerials in the surveil

38、lance program as capsule space permits.5.2.2 Material SamplingA minimum test program shallconsist of the material selected in 5.2.1, taken from thefollowing: (1) base metal from the actual plate(s) or forging(s)used in the reactor vessel, and (2) weld metal(s) made with thesame heat of weld wire and

39、 lot of flux and by the same weldingprocedure as that used for the reactor vessel welds. The basemetal used to fabricate the weldment(s) shall be one of the basemetals included in the surveillance program. Surveillance testmaterials shall be full thickness samples.NOTE 4Experience has shown that it

40、is no longer necessary to includethe heat-affected zone material in the surveillance program. However, it isrecommended that the heat-affected-zone material be included with thearchives (see 5.2.5).5.2.3 Fabrication HistoryThe fabrication history (austen-itizing, quench and tempering, and post-weld

41、heat treatment) ofthe test materials shall be fully representative of the fabricationhistory of the reactor vessel materials selected in 5.2.1 andshall be recorded.5.2.4 Chemical Analysis RequirementsThe chemicalanalysis required by the appropriate product specifications forthe surveillance test mat

42、erials (base metal and as-depositedweld metal) shall be recorded and shall include phosphorus (P),sulfur (S), copper (Cu), vanadium (V), silicon (Si), manganese(Mn), and nickel (Ni), as well as all other alloying and residualelements commonly analyzed for in low-alloy steel products.The product anal

43、ysis shall be as described in Test MethodA751 and verified by analyzing samples selected from the basemetal and the as-deposited weld metal.5.2.5 Archive MaterialsTest stock to fill up to six addi-tional capsules beyond the minimum number required fortesting with test specimens of the base metal and

44、 weldmaterials used in the program shall be retained with fulldocumentation and identification. This stock should be in theform of full-thickness sections of the original materials (plates,forgings, and welds) except specimens included in standbycapsules. It is recommended that the heat-affected-zon

45、e mate-rial associated with the archive weld material be retained toprovide supplemental data.5.3 Test Specimens5.3.1 Type of SpecimensCharpy V-notch specimens cor-responding to the Type A specimen described in Test MethodsA370 and E23 shall be used. Tension specimens of the type,size, and shape des

46、cribed in Test Methods A370 and E8/E8Mare recommended. The gage section of irradiated and unirra-diated tension specimens shall be of the same size and shape.Fracture toughness test specimens shall be consistent with theguidelines provided in Test Methods E1820 and E1921.5.3.2 Specimen Orientation a

47、nd LocationTension,Charpy and fracture toughness specimens representing the basemetal shall be removed from about the quarter-thickness (14-Tor34-T) locations. Material from the mid- thickness of the basemetal shall not be used for test specimens. Specimens repre-senting weld metal may be removed fr

48、om any locationthroughout the thickness with the exception of locations within12.7 mm (12 in.) of the root or surfaces of the welds. Specialattention must be given to defining the root of the weld in orderto avoid taking weld metal that is different in composition fromthe surveillance weld metal. Th

49、e tension and Charpy speci-mens from base metal shall be oriented so that the major axisof the specimen is parallel to the surface and normal to theprincipal rolling direction for plates, or normal to the majorworking direction for forgings shown in Test Method E23,Annex A5 (T-L orientation). The axis of the notch of theCharpy specimen for base metal and weld metal shall beoriented perpendicular to the surface of the material. Therecommended orientation of the weld metal specimens isshown in Fig. 1. Weld metal tension specimens may beoriented in the