1、Designation:E100516Standard Test Method forApplication and Analysis of Radiometric Monitors forReactor Vessel Surveillance1This standard is issued under the fixed designation E1005;the number immediately following the designation indicates the year oforiginal adoption or,in the case of revision,the
2、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 test method describes procedures for measuring thespecific activities of radioactive nuclides produced in radi
3、o-metric monitors(RMs)by nuclear reactions induced duringsurveillance exposures for reactor vessels and support struc-tures.More detailed procedures for individual RMs are pro-vided in separate standards identified in 2.1 and in Refs(1-5).2The measurement results can be used to define correspondingn
4、eutron induced reaction rates that can in turn be used tocharacterize the irradiation environment of the reactor vesseland support structure.The principal measurement technique ishigh resolution gamma-ray spectrometry,although X-ray pho-ton spectrometry and Beta particle counting are used to a lesse
5、rdegree for specific RMs(1-29).1.1.1 The measurement procedures include corrections fordetector background radiation,random and true coincidencesumming losses,differences in geometry between calibrationsource standards and the RMs,self absorption of radiation bythe RM,other absorption effects,radioa
6、ctive decay corrections,and burn out of the nuclide of interest(6-26).1.1.2 Specific activities are calculated by taking into ac-count the time duration of the count,the elapsed time betweenstart of count and the end of the irradiation,the half life,themass of the target nuclide in the RM,and the br
7、anchingintensities of the radiation of interest.Using the appropriatehalf life and known conditions of the irradiation,the specificactivities may be converted into corresponding reaction rates(2-5,28-30).1.1.3 Procedures for calculation of reaction rates from theradioactivity measurements and the ir
8、radiation power timehistory are included.A reaction rate can be converted toneutron fluence rate and fluence using the appropriate integralcross section and effective irradiation time values,and,withother reaction rates can be used to define the neutron spectrumthrough the use of suitable computer p
9、rograms(2-5,28-30).1.1.4 The use of benchmark neutron fields for calibration ofRMs can reduce significantly or eliminate systematic errorssince many parameters,and their respective uncertainties,required for calculation of absolute reaction rates are commonto both the benchmark and test measurements
10、 and therefore areself canceling.The benchmark equivalent fluence rates,for theenvironment tested,can be calculated from a direct ratio of themeasured saturated activities in the two environments and thecertified benchmark fluence rate(2-5,28-30).1.2 This method is intended to be used in conjunction
11、 withASTM Guide E844.The following existing or proposedASTMpractices,guides,and methods are also directly involved in thephysics-dosimetry evaluation of reactor vessel and supportstructure surveillance measurements:E706 Master Matrix for Light-Water Reactor Pressure VesselSurveillance Standards,E706
12、(O)3E853 Analysis and Interpretation of Light-Water ReactorSurveillance Results,E706(IA)3E693 Practice for Characterizing Neutron Exposures in Ironand Low Alloy Steels in Terms of Displacements Per Atom(DPA),E706(ID)3E185 Practice for Conducting Surveillance Tests for Light-Water Nuclear Power React
13、or Vessels,E706(IF)3E1035 Practice for Determining Radiation Exposure forNuclear Reactor Vessel Support Structures,E706(IG)3E636 Practice for Conducting Supplemental SurveillanceTests for Nuclear Power Reactor Vessels,E706(IH)3E2956 Guide for Monitoring the Neutron Exposure of LWRReactor Pressure Ve
14、ssels3E944 Guide for Application of Neutron Spectrum Adjust-ment Methods in Reactor Surveillance,E706(IIA)3E1018 Guide for Application of ASTM Evaluated CrossSection and Data File,E706(IIB)3E482 Guide for Application of Neutron Transport Methodsfor Reactor Vessel Surveillance,E706(IID)3E2005 Guide f
15、or the Benchmark Testing of Reactor VesselDosimetry in Standard and Reference Neutron FieldsE2006 Guide for the Benchmark Testing of Light WaterReactor Calculations1This test method is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applications and is the direct responsibility
16、 of SubcommitteeE10.05 on Nuclear Radiation Metrology.Current edition approved Oct.1,2016.Published November 2016.Originallyapproved in 1997.Last previous edition approved in 2015 as E1005 15.DOI:10.1520/E1005-16.2The boldface numbers in parentheses refer to the list of references appended tothis method.3The reference in parentheses refers to Section 5 as well as Figs.1 and 2 ofMatrix E706.Copyright ASTM International,100 Barr Harbor Drive,PO Box C700,West Conshohocken,PA 19428-2959.United State
