ASTM D7727-2011(2016) 7886 Standard Practice for Calculation of Dose Equivalent Xenon (DEX) for Radioactive Xenon Fission Products in Reactor Coolant《反应堆冷却剂中氙裂变产物剂量当量疝(DEX)计算的标准操作规.pdf
《ASTM D7727-2011(2016) 7886 Standard Practice for Calculation of Dose Equivalent Xenon (DEX) for Radioactive Xenon Fission Products in Reactor Coolant《反应堆冷却剂中氙裂变产物剂量当量疝(DEX)计算的标准操作规.pdf》由会员分享,可在线阅读,更多相关《ASTM D7727-2011(2016) 7886 Standard Practice for Calculation of Dose Equivalent Xenon (DEX) for Radioactive Xenon Fission Products in Reactor Coolant《反应堆冷却剂中氙裂变产物剂量当量疝(DEX)计算的标准操作规.pdf(3页珍藏版)》请在麦多课文档分享上搜索。
1、Designation: D7727 11 (Reapproved 2016)Standard Practice forCalculation of Dose Equivalent Xenon (DEX) for RadioactiveXenon Fission Products in Reactor Coolant1This standard is issued under the fixed designation D7727; the number immediately following the designation indicates the year oforiginal ad
2、option or, in the case of revision, 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 applies to the calculation of the doseequivalent to133Xe
3、 in the reactor coolant of nuclear powerreactors resulting from the radioactivity of all noble gas fissionproducts.1.2 The values stated in inch-pound units are to be regardedas standard. The values given in parentheses are mathematicalconversions to SI units that are provided for information onlyan
4、d are not considered standard.1.3 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 to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitation
5、s prior to use.2. Referenced Documents2.1 ASTM Standards:2D3648 Practices for the Measurement of RadioactivityD7282 Practice for Set-up, Calibration, and Quality Controlof Instruments Used for Radioactivity Measurements3. Terminology3.1 Definitions:3.1.1 DOSE-EQUIVALENT XE-133 (DEX), nshall be that1
6、33Xe concentration (microcuries per gram) that alone wouldproduce the same acute dose to the whole body as thecombined activities of noble-gas nuclides85mKr,85Kr,87Kr,88Kr,131mXe,133mXe,133Xe,135mXe,135Xe, and138Xe actuallypresent.3.1.1.1 DiscussionThis is the general definition of DEX.Each utility
7、may have adopted modifications to this definitionthrough agreement with the U.S. Nuclear Regulatory Commis-sion (U.S. NRC). The definition as approved for each utility bythe U.S. NRC is the one that should be applied to thecalculations in this practice.4. Summary of Practice4.1 A sample of fresh rea
8、ctor coolant is analyzed for noblegas activities using gamma ray spectrometry. The individualactivity of each detectable radioactive fission gas is divided bya factor that normalizes its dose to that of133Xe. This practiceis to replace the previous practice of calculating the reactorcoolant calculat
9、ion when allowed by the plants revisedtechnical specifications. The quantity DEX is acceptable froma radiological dose perspective since it will result in a limitingcondition of operation (LCO) that more closely relates thenon-iodine RCS activity limits to the dose consequence analy-ses which form t
10、heir bases.NOTE 1It is incumbent on the licensee to ensure that the doseconversion factors (DCFs) used in the determination of DEX are consis-tent with the DCFs used in the applicable dose consequence analysis usedby the plant in their dose calculation manual for radioactive releases.5. Significance
11、 and Use5.1 Each power reactor has a specific DEX value that istheir technical requirement limit. These values may vary fromabout 200 to about 900 Ci/g based upon the height of theirplant vent, the location of the site boundary, the calculatedreactor coolant activity for a condition of 1 % fuel defe
12、cts, andgeneral atmospheric modeling that is ascribed to that particularplant site. Should the DEX measured activity exceed thetechnical requirement limit, the plant enters an LCO requiringaction on plant operation by the operators.5.2 The determination of DEX is performed in a similarmanner to that
13、 used in determining DEI, except that thecalculation of DEX is based on the acute dose to the wholebody and considers the noble gases85mKr,85Kr,87Kr,88Kr,131mXe,133mXe,133Xe,135mXe,135Xe, and138Xe which aresignificant in terms of contribution to whole body dose.5.3 It is important to note that only
14、fission gases areincluded in this calculation, and only the ones noted in Table 1.For example83mKr is not included even though its half-life is1.86 hours. The reason for this is that this radionuclide cannot1This practice is under the jurisdiction of ASTM Committee D19 on Water andis the direct resp
15、onsibility of Subcommittee D19.04 on Methods of RadiochemicalAnalysis.Current edition approved Nov. 1, 2016. Published November 2016. Originallyapproved in 2011. Last previous edition approved in 2011 as D7727 111. DOI:10.1520/D7727-11R16.2For referenced ASTM standards, visit the ASTM website, www.a
16、stm.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.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States1be easil
17、y determined by gamma spectrometry (low energyX-rays at 32 and 9 keV) and its dose consequence is vanish-ingly small compared to the other, more prevalent kryptonradionuclides.5.4 Activity from41Ar,19F,16N, and11C, all of whichpredominantly will be in gaseous forms in the RCS, are notincluded in thi
18、s calculation.5.5 If a specific noble-gas radionuclide is not detected, itshould be assumed to be present at the minimum-detectableactivity. The determination of DOSE-EQUIVALENT XE-133shall be performed using effective dose-conversion factors forair submersion listed in Table III.1 of EPA Federal Gu
19、idanceReport No. 12,3or the average gamma-disintegration energiesas provided in ICRP Publication 38 (“Radionuclide Transfor-mations”) or similar source.6. Interferences6.1 The analytical determination of the radionuclides usedfor this calculation is made by gamma ray spectrometry.Commercially availa
20、ble software is generally used to performthe spectrum analysis and data reduction. However, there canbe significant number of interferences from gamma ray emit-ters with multiple gamma ray emissions. The user mustcarefully select the appropriate interference-free gamma rayenergy for each radionuclid
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