ASTM E1297-2008 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium《用铌辐射激活法测量快中子反应率的标准试验方法》.pdf

《ASTM E1297-2008 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium《用铌辐射激活法测量快中子反应率的标准试验方法》.pdf》由会员分享，可在线阅读，更多相关《ASTM E1297-2008 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium《用铌辐射激活法测量快中子反应率的标准试验方法》.pdf（6页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: E 1297 08Standard Test Method forMeasuring Fast-Neutron Reaction Rates by Radioactivationof Niobium1This standard is issued under the fixed designation E 1297; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year o

2、f 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 measuringreaction rates by the activation reaction93Nb(n,n8)93mNb.1.2 This

3、 activation reaction is useful for monitoring neu-trons with energies above approximately 0.5 MeV and forirradiation times up to about 30 years.1.3 With suitable techniques, fast-neutron reaction rates forneutrons with energy distribution similar to fission neutronscan be determined in fast-neutron

4、fluences above about1016cm2. In the presence of high thermal-neutron fluence rates(1012cm2s1), the transmutation of93mNb due to neutroncapture should be investigated. In the presence of high-energyneutron spectra such as are associated with fusion and spalla-tion sources, the transmutation of93mNb b

5、y reactions such as(n,2n) may occur and should be investigated.1.4 Procedures for other fast-neutron monitors are refer-enced in Practice E 261.1.5 Fast-neutron fluence rates can be determined from thereaction rates provided that the appropriate cross sectioninformation is available to meet the accu

6、racy requirements.1.6 The values stated in SI units are to be regarded asstandard. No other units of measurement are included in thisstandard.1.7 This standard does not purport to address all of thesafety concerns, if any, associated with its use. It is theresponsibility of the user of this standard

7、 to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM Standards:2D 1193 Specification for Reagent WaterE 170 Terminology Relating to Radiation Measurementsand DosimetryE 181 Test Methods for Dete

8、ctor Calibration and Analysisof RadionuclidesE 185 Practice for Design of Surveillance Programs forLight-Water Moderated Nuclear Power Reactor VesselsE 261 Practice for Determining Neutron Fluence, FluenceRate, and Spectra by Radioactivation TechniquesE 262 Test Method for Determining Thermal Neutro

9、n Re-action and Fluence Rates by Radioactivation TechniquesE 844 Guide for Sensor Set Design and Irradiation forReactor Surveillance, E 706(IIC)E 944 Guide for Application of Neutron Spectrum Adjust-ment Methods in Reactor Surveillance, E 706 (IIA)E 1005 Test Method forApplication andAnalysis of Rad

10、io-metric Monitors for Reactor Vessel Surveillance, E706(IIIA)E 1006 Practice for Analysis and Interpretation of PhysicsDosimetry Results for Test Reactors, E 706(II)E 1018 Guide for Application of ASTM Evaluated CrossSection Data File, Matrix E 706 (IIB)3. Terminology3.1 DefinitionsThe definitions

11、stated in TerminologyE 170 are applicable to this test method.4. Summary of Test Method4.1 High purity niobium is irradiated in a neutron fieldproducing radioactive93mNb from the93Nb(n,n8)93mNb reac-tion. The metastable state decays to the ground state by thevirtual emission of 30 keV gamma rays tha

12、t are all internallyconverted giving rise to the actual emission of orbital electronsfollowed by X rays.4.2 Sources of the irradiated niobium are prepared for X rayor liquid scintillation counting.4.3 The X rays emitted as a result of the decay of93mNb arecounted, and the reaction rate, as defined i

13、n Practice E 261,iscalculated from the decay rate and irradiation conditions.4.4 The neutron fluence rate may then be calculated fromthe appropriate spectral-weighted neutron activation crosssection as defined by Practice E 261.1This test method is under the jurisdiction ofASTM Committee E10 on Nucl

14、earTechnology and Applications and is the direct responsibility of SubcommitteeE10.05 on Nuclear Radiation Metrology.Current edition approved July 1, 2008. Published August 2008. Originallyapproved in 1989. Last previous edition approved in 2002 as E 1297 02.2For referenced ASTM standards, visit the

15、 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 19428-2959, U

16、nited States.5. Significance and Use5.1 Refer to Practice E 261 for a general discussion of thedetermination of decay rates, reaction rates, and neutronfluence rates with threshold detectors (1-29).3Refer to PracticeE 1006, Practice E 185 and Guide E 1018 for the use andapplication of results obtain

17、ed by this test method.(34-36)5.2 The half-life of93mNb is 5730 6 220 days (30) and hasa K X-ray emission probability of 0.1099 6 0.0025 per decay(30). The Kaand KbX-rays of niobium are at 16.521316.152and 18.61818.953 keV, respectively. The recommended93Nb(n,n8)93mNb cross section comes from the IR

18、DF-90 crosssection compendium (31), was drawn from the RRDF-98 crosssection evaluations (37) and is shown in Fig. 1.5.3 Chemical dissolution of the irradiated niobium to pro-duce very low mass-per-unit area sources is an effective way toobtain consistent results. The direct counting of foils or wire

19、scan produce satisfactory results provided appropriate methodsand interpretations are employed. It is possible to use liquidscintillation methods to measure the niobium activity providedthe radioactive material can be kept uniformly in solution andappropriate corrections can be made for interfering

20、activities.5.4 The measured reaction rates can be used to correlateneutron exposures, provide comparison with calculated reac-tion rates, and determine neutron fluences. Reaction rates canbe determined with greater accuracy than fluence rates becauseof the current uncertainty in the cross section ve

21、rsus energyshape.5.5 The93Nb(n,n8)93mNb reaction has the desirable proper-ties of monitoring neutron exposures related to neutron damageof nuclear facility structural components. It has an energyresponse range corresponding to the damage function of steeland has a half-life sufficiently long to allo

22、w its use in very longexposures (up to about 40 years). Monitoring long exposures isuseful in determining the long-term integrity of nuclear facilitycomponents.6. Interferences6.1 Pure niobium in the forms of foil and wire is availableand easily handled as a metal. When thin niobium is irradiated,it

23、 may become brittle and fragile, thus requiring carefulhandling or encapsulation to prevent damage or loss of theniobium. Refer to Guide E 844 for the selection, irradiation,and quality control of neutron dosimeters.6.2 There are some distinct advantages and limitations tothree measurement technique

24、s identified in 5.3.Itistheresponsibility of the user to evaluate these and determine theoptimum technique for the situation.6.2.1 Low mass source X-ray spectrometry advantagesinclude sufficient energy resolution to eliminate other X-rayemissions, stable long life sources, reduced interference fluo-

25、rescence due to other radionuclides, small and precise back-ground corrections, and minimal X-ray source self-absorptioncorrections. Limitations are low counting efficiency, complexsource preparation, and use of hazardous chemicals.6.2.2 Direct X-ray spectrometry of metal (foil or wire)sources has t

26、he advantages of simple source preparation, stablelong life sources, sufficient energy resolution to eliminate otherX-ray emissions, small and precise background corrections,and no use of hazardous chemicals. Limitations are lowcounting efficiency, large X-ray source self-absorption correc-tions, la

27、rger corrections for interference fluorescence due to theother radionuclides, and source geometry control.6.2.3 Liquid scintillation counting advantages include veryhigh detection efficiency, reproducible source preparation, andno source self absorption corrections. Limitations includespecialized ca

28、libration techniques to reduce interference fromother radionuclides, limited source stability, use of hazardouschemicals, and disposal of hazardous chemical waste.3The boldface numbers in parentheses refer to the list of references at the end ofthis test method.FIG. 1 IRDF-90 Cross Section Versus En

29、ergy for the93Nb(n,n*)93mNb ReactionE12970827. Apparatus7.1 X-ray Spectrometer, using a Si(Li) detector or a Gedetector and a multichannel pulse-height analyzer. For moreinformation, refer to Test Methods E 181 and E 1005.7.2 Precision Balance, able to achieve the required accu-racy.7.3 Beakers, 50

30、mL polyethylene; pycnometer (weighingbottle), 50 mL polyethylene; volumetric pipets, 10 L to 5 mL.7.4 Gamma Ray Spectrometer, using a Ge detector and amultichannel pulse-height analyzer. Refer to Test MethodE 181.7.5 Liquid Scintillation Counter.8. Reagents and Materials8.1 Purity of ReagentsReagent

31、 grade chemicals shall beused in all tests. Unless otherwise indicated, it is intended thatall reagents conform to the specifications of the Committee onAnalytical Reagents of the American Chemical Society, wheresuch specifications are available.4Other grades may be used,provided it is first ascerta

32、ined that the reagent is of sufficientlyhigh purity to permit its use without lessening the accuracy ofthe determination.8.2 Purity of WaterUnless otherwise indicated, any waterused shall be understood to mean reagent water as defined byType I of Specification D 1193.8.3 Hydrofluoric AcidConcentrate

33、d (32M) hydrofluoricacid (HF).8.4 Nitric AcidConcentrated (16M) nitric acid (HNO3).8.5 Niobium MetalThe purity of the niobium is importantin that no impurities (such as tantalum) should be present toproduce long-lived radionuclides that interfere with the93mNbactivity determination. To avoid problem

34、s from tantalum, theniobium should have the lowest tantalum content possible.Niobium metal in the form of foil and wire with tantalumcontent of about 5 ppm (parts per million) or less is obtainableand can be used under most conditions. The niobium materialshould be tested for interfering radioactivi

35、ty by neutron acti-vation techniques.8.6 Encapsulation MaterialThe encapsulation material(such as quartz, stainless steel, aluminum, etc.) should beselected to prevent corrosion of the niobium during irradiationand to be compatible with the irradiation environment andpost-irradiation handling. If th

36、ermal and epithermal neutronfilters or shrouds are used, these materials (such as cadmium,tantalum, gadolinium, etc.) must also be compatible with theencapsulation and irradiation environment.8.7 Analytical PaperAnalytical grade filter paper of uni-form thickness (about 0.076 cm) and density (about

37、8 mgcm2). The paper can be cut or obtained precut to the desiredsize (usually between 0.5 and 1.5 cm diameter) that iscompatible with the activity concentration of the solution andthe counting conditions. The paper should be able to absorb asmuch liquid as is necessary and not decompose from the aci

38、d.TFE-fluorocarbon rings with an inside diameter matching theoutside diameter of the filter paper disks so they fit togetherwith light contact.8.8 Support and Cover MaterialsThin plastic film andplastic tape materials are useful to support and cover the filterpaper sources. They should be strong eno

39、ugh to contain thesources and thin enough to minimize attenuation of the X rays.8.9 Source HolderA source holder must be used toaccurately and reproducibly position the sources for the count-ing geometry to be used. The source holder should be con-structed of low density materials such as aluminum o

40、r plastic.8.10 Liquid Scintillation MaterialsVials, emulsion scin-tillant (xylene-based), chelating agent (di-2-ethylhexyl phos-phoric acid).9. Procedure9.1 Determine the size and shape of the niobium samplebeing irradiated. Consider the convenience in handling andavailable irradiation space. Ensure

41、 that sufficient93mNb activ-ity will be produced to permit accurate radioassay. Typically,samples of 0.2 to 20 mg of niobium may be used, but apreliminary calculation of the expected production of93mNbwill aid in selecting the appropriate mass for the irradiation.9.2 Accurately weigh the niobium sam

42、ple being irradiated.9.3 Encapsulate the niobium sample so that it can beretrieved and identified following the irradiation. Record thesample identification, sample weight, and exact details of theencapsulation. Shroud the niobium with neutron filter materialif necessary. If the thermal-to-fast neut

43、ron fluence rate ratio ishigh (greater than 5) or the tantalum impurity is high (greaterthan 10 ppm), use neutron filter materials, if possible.9.4 Irradiate the niobium samples. Keep an accurate recordof the irradiation history including neutron level versus time,starting and ending time of the irr

44、adiation, and the periodswhen the neutron level is zero. Record the spatial position ofthe sample in the irradiation facility.9.5 After the irradiation, retrieve and identify the irradiatedsample. Take necessary precautions to avoid personnel over-exposure to radiation and the spread of radioactive

45、contamina-tion.9.6 A waiting time between the end of irradiation and thestart of counting may be necessary to allow92mNb or95Nb, orboth, to decay to an insignificant level. Check the samples foractivity from contamination by other materials or reactions (seeTest Method E 262) and for any material ad

46、hering to thesample. Check the weight of the sample. If necessary, cleanand reweigh the sample.9.7 X-Ray Source Preparation and Counting:9.7.1 If the metal is being dissolved and reduced to a lowmass-per-unit area source, dissolve the sample by placing it ina preweighed 50 mL polyethylene or TFE-flu

47、orocarbon (non-wettable) beaker and adding enough concentrated hydrofluoricacid to cover the sample (usually about 1 to 10 mLof HF).Addconcentrated nitric acid dropwise to start dissolution; asdissolution slows, add additional drops to maintain a controlledslow rate of dissolution until the entire s

48、ample dissolves. Afterdissolution is complete, bring the final volume of solution tothe desired amount by adding distilled water. Weigh the4“Reagent Chemicals,American Chemical Society Specifications,”Am. Chemi-cal Soc., Washington, DC. For suggestions on the testing of reagents not listed bytheAmer

49、ican Chemical Society, see “Reagent Chemicals and Standards,” by JosephRosin, D. Van Nostrand Co., Inc., New York, NY, and the “United StatesPharmacopeia.”E1297083solution in the beaker if mass aliquoting is used.Apreweighedpolyethylene pycnometer (weighing bottle) is recommendedfor mass aliquoting. The ratio of the niobium mass to thesolution mass determines the concentration of niobium in thesolution. When transferring the solution from one container toanother, ensure that all of the solution is transferred by usingmultiple rinses. Use accurately calibrated pipe