ASTM E1214-2011 Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance E 706 (IIIE)《反应堆容器监测所用的熔丝温度监测器的使用标准指南 E 706(IIIE)》.pdf

《ASTM E1214-2011 Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance E 706 (IIIE)《反应堆容器监测所用的熔丝温度监测器的使用标准指南 E 706(IIIE)》.pdf》由会员分享，可在线阅读，更多相关《ASTM E1214-2011 Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance E 706 (IIIE)《反应堆容器监测所用的熔丝温度监测器的使用标准指南 E 706(IIIE)》.pdf（3页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: E1214 11Standard Guide forUse of Melt Wire Temperature Monitors for Reactor VesselSurveillance, E 706 (IIIE)1This standard is issued under the fixed designation E1214; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, th

2、e 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 guide describes the application of melt wire tem-perature monitors and their use for reactor vessel sur

3、veillanceof light-water power reactors as called for in Practices E185and E2215.1.2 The purpose of this guide is to recommend the selectionand use of the common melt wire technique where thecorrespondence between melting temperature and compositionof different alloys is used as a passive temperature

4、 monitor.Guidelines are provided for the selection and calibration ofmonitor materials; design, fabrication, and assembly of moni-tor and container; post-irradiation examinations; interpretationof the results; and estimation of uncertainties.1.3 The values stated in SI units are to be regarded assta

5、ndard. The values given in parentheses are mathematicalconversions to inch-pound units that are provided for informa-tion only and are not considered standard.1.4 This standard does not purport to address all of thesafety concerns, if any, associated with its use. It is theresponsibility of the user

6、 of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use. (See Note 1.)2. Referenced Documents2.1 ASTM Standards:2E185 Practice for Design of Surveillance Programs forLight-Water Moderated Nuclear Power Reactor Ve

7、sselsE706 Master Matrix for Light-Water Reactor Pressure Ves-sel Surveillance Standards, E 706(0)3E794 Test Method for Melting And Crystallization Tem-peratures By Thermal AnalysisE900 Guide for Predicting Radiation-Induced TransitionTemperature Shift in Reactor Vessel Materials, E706 (IIF)E2215 Pra

8、ctice for Evaluation of Surveillance Capsulesfrom Light-Water Moderated Nuclear Power Reactor Ves-sels3. Significance and Use3.1 Temperature monitors are used in surveillance capsulesin accordance with Practice E2215 to estimate the maximumvalue of the surveillance specimen irradiation temperature.T

9、emperature monitors are needed to give evidence of overheat-ing of surveillance specimens beyond the expected tempera-ture. Because overheating causes a reduction in the amount ofneutron radiation damage to the surveillance specimens, thisoverheating could result in a change in the measured properti

10、esof the surveillance specimens that would lead to an unconser-vative prediction of damage to the reactor vessel material.3.2 The magnitude of the reduction of radiation damagewith overheating depends on the composition of the materialand time at temperature. Guide E900 provides an acceptedmethod fo

11、r quantifying the temperature effect. Because theevidence from melt wire monitors gives no indication of theduration of overheating above the expected temperature asindicated by melting of the monitor, the significance ofoverheating events cannot be quantified on the basis oftemperature monitors alo

12、ne. Indication of overheating doesserve to alert the user of the data to further evaluate theirradiation temperature exposure history of the surveillancecapsule.3.3 This guide is IIIE of Master Matrix E706 that relatesseveral standards used for irradiation surveillance of lightwater reactor vessel m

13、aterials. It is intended primarily toamplify the requirements of Practice E185 in the design oftemperature monitors for the surveillance program. It may alsobe used in conjunction with Practice E2215 to evaluate thepost-irradiation test measurements4. Selection and Calibration of Monitor Materials4.

14、1 Selection of Monitor Materials:4.1.1 Materials selected for temperature monitors shall pos-sess unique melting temperatures. Since composition, andparticularly the presence of impurities, strongly influencemelting temperature, the fabricated monitor materials shallconsist of either metals of purit

15、y 99.9 % or greater or eutectic1This guide 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 July 1, 2011. Published September 2011.

16、 Originallyapproved in 1987. Last previous edition approved in 2006 as E121406. DOI:10.1520/E1214-11.2The reference Master Matrix designation in parentheses refers to Section 5, aswell as Figs. 1 and 2 of Matrix E706.3Withdrawn. The last approved version of this historical standard is referencedon w

17、ww.astm.org.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.alloys such that the measured melting temperature is within63C (65F) of the recognized melting temperature.Transmutation-induced changes of the monitor materials sug-gested

18、in 4.1.2 are not considered significant for fluenceexposures up to 1 3 1020n/cm2(E 1 MeV) relative to thegoal of these temperature monitors in flagging deviations fromexpected temperatures.4.1.2 The monitor materials in Table 1 provide temperatureindications in the range of 266 to 327C (511 to 621F)

19、. Othermetals or alloys may be selected for the temperatures ofinterest provided the monitor materials meet the technicalrequirements of this guide.4.1.3 The chosen monitor materials shall be carefully evalu-ated for radiological health hazards.NOTE 1It is beyond the scope of this guide to provide s

20、afety andhealth criteria, and the user is cautioned to seek further guidance.4.2 Calibration of Monitor Materials Each lot of monitormaterials shall be calibrated by melting tests to establish theactual melting temperatures. The melting temperature testsshall be conducted in accordance with Test Met

21、hod E794.Ifanalternate method of calibration is used, the procedure andequipment must be described, the resultant mean values anduncertainties must be reported, and traceability to standardsmust be declared.5. Design, Fabrication, and Assembly of Monitor andContainer5.1 The design of the monitor and

22、 its container shall ensurethat the maximum temperature of the surveillance specimens isdetermined within 610C (618F).5.2 The design shall provide for a minimum of one set ofmonitors for each surveillance capsule. Additional sets ofmonitors are recommended to characterize the in-service axialtempera

23、ture profiles necessary to determine the maximumtemperature of each surveillance specimen.5.3 The design of the monitor and its container shall ensurethat the monitor will readily sense the environmental tempera-ture of the surveillance specimens and yet not be subject to anyinfluences from fabricat

24、ion or assembly or even post-serviceexamination. The monitors typically consist of melt wirespositioned adjacent to or among the surveillance specimens.5.4 The quantity of monitors within each set shall beadequate to identify any temperature excursion of 10C (18F)up to the highest potential temperat

25、ure, such as 330C (626F).It is recommended that monitors be selected to measuretemperature at intervals of 5 to 12C (9 to 22F). At least onemonitor shall remain intact throughout the service life; there-fore the highest temperature monitor shall possess a meltingtemperature greater than the highest

26、anticipated temperature.5.5 Fabrication and assembly of the monitors and containersshall protect and maintain the integrity of each temperaturemonitor and its ability to respond by melting at the environ-mental temperature of the surveillance specimens correspond-ing to the monitors melting temperat

27、ure. The monitors andcontainers shall be designed, fabricated and assembled toensure that the monitors melt at a temperature within 63C(5F) of the environmental temperature of the specimens.5.6 Identification of each monitor, its material and meltingtemperature, and its orientation and location in t

28、he surveillancecapsule shall be maintained. Provision for means of verifica-tion shall be done by design.6. Post-Irradiation Examination6.1 Following irradiation, the temperature monitors shall beexamined for evidence of melting to establish the maximumexposure temperature of the encapsulated survei

29、llance speci-mens. Precautions should be taken while recovering the moni-tors from the surveillance capsule and during subsequentexamination.6.1.1 The monitor design and method of encapsulation shallbe considered in the recovery procedure to ensure that themonitors are not damaged and that the origi

30、nal identity ofindividual monitors and their location is maintained.6.1.2 Recovery and examination of the monitors should beperformed remotely or with sufficient shielding to protect theoperator from unnecessary radiation exposure.6.2 Evaluation of the temperature monitors after service forevidence

31、of melting should be performed using suitable equip-ment that is dependent on the design of the monitor containerand the examination facility. When visual inspection of themonitors is possible, such as with periscopes, each monitorshall be examined and the results recorded. When possible,photographi

32、c records should be made of each monitor or set ofmonitors. When visual inspection is not practical or conclusive,radiography or metallographic examination may be necessary.Destructive examination should be performed only if furtherconfirmation of the melting temperature is necessary.6.3 The monitor

33、s shall be evaluated on the following basis:6.3.1 UnmeltedNo evidence of melting of any portion ofthe monitor.6.3.2 Partially MeltedAny evidence of any melting ofany portion of the monitor.6.3.3 Fully MeltedEvidence that the entire monitor wassubject to melting.6.4 If there is reason to question the

34、 results, monitors shouldbe reevaluated after completion of the post-irradiation exami-nation to ensure that there was no change in the meltingtemperature. This verification of melting temperature may beperformed as described in 4.2.7. Interpretation7.1 The design of the melt wire configuration shou

35、ld pre-vent ambiguities as to incipient melting. However, there maybe circumstances where melting is questionable. Change inshape, slumping, and segmenting are indications of melting.TABLE 1 Monitor Material Melting TemperaturesMonitor Material,Weight %Melting Temperature,CMelting Temperature,FCd17.

36、4 Zn 266 511Au20.0 Sn 280 536Pb5.0 Ag5.0 Sn 292 558Pb2.5 Ag 304 579Pb1.5 Ag1.0 Sn 309 588Pb1.75 Ag0.75 Sn 310 590Cd1.2 Cu 314 597Cd 321 610Pb 327 621E1214 112When initial examination results are uncertain, this shall bedocumented. Further nondestructive and destructive examina-tions may be performed

37、 if warranted to verify the condition ofthe monitor.7.2 The condition of the monitors should be consistentaccording to axial position and expected relative temperatures.7.3 The range of possible maximum service temperatures ofthe surveillance specimen shall be estimated and documented,based upon the

38、 indications provided by the temperature moni-tors. The temperature estimate should consider the design ofthe monitor and container, the location of specimens relative tothe monitors, and potential temperature gradients.7.4 Discrepancies between the temperature monitor resultsand historical service

39、conditions shall be assessed and de-scribed.8. Estimation of Uncertainties8.1 Uncertainties arise from limitations in precision and biasin determining the initial melting temperatures of each monitor,the ability of the monitor to accurately indicate the environ-mental temperature, the relationship i

40、n temperature betweenthe monitors and the specimens, and the bias in discriminatingmelting.8.2 All known and estimated uncertainties, including adescription of their determination, shall be reported with theestimated maximum exposure temperatures.8.3 Uncertainties resulting from unresolved ambiguiti

41、esshall be described. Probable causes and subsequent implica-tions should be stated.9. Report9.1 In addition to the reporting requirements of PracticesE185 and E2215, the following information shall be reported:9.1.1 Description of the temperature monitors includingchemical composition of the monito

42、r melt wires and theirrespective melting temperatures with uncertainties, containerdesign, identification, and location in the irradiation capsule.9.1.2 Results of the post-service evaluation in which eachmonitor condition is characterized as unmelted, partiallymelted, or fully melted.9.1.3 The esti

43、mated maximum exposure temperature rangeof the surveillance specimens and the associated uncertainties.9.1.4 The agreement between the temperature monitor re-sults and the historical service conditions and description ofany anomalies found while recovering, examining, or evaluat-ing the monitors.9.1

44、.5 Results of any additional examinations, if performed,to resolve inconsistent monitor results.9.2 The following additional documentation should be re-ported if available:9.2.1 Photographs of each irradiated temperature monitorthat document the visual observations.9.2.2 Preirradiation test results

45、used to certify the meltingtemperatures of each monitor type.9.2.3 Test results, if performed, verifying post-irradiationmelting temperature for each monitor.10. Keywords10.1 nuclear reactor vessels; neutron irradiation; surveil-lance (of nuclear reactor vessels)ASTM International takes no position

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47、is standard is subject to revision at any time by the responsible technical committee and must be reviewed every five years andif not revised, either reapproved or withdrawn. Your comments are invited either for revision of this standard or for additional standardsand should be addressed to ASTM Int

48、ernational Headquarters. Your comments will receive careful consideration at a meeting of theresponsible technical committee, which you may attend. If you feel that your comments have not received a fair hearing you shouldmake your views known to the ASTM Committee on Standards, at the address shown

49、 below.This standard is copyrighted by ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959,United States. Individual reprints (single or multiple copies) of this standard may be obtained by contacting ASTM at the aboveaddress or at 610-832-9585 (phone), 610-832-9555 (fax), or serviceastm.org (e-mail); or through the ASTM website(www.astm.org). Permission rights to photocopy the standard may also be secured from the ASTM website (www.astm.org/COPYRIGHT/).E1214 113