ASTM D7727-2011e1 4379 Standard Practice for Calculation of Dose Equivalent Xenon &40 DEX&41 for Radioactive Xenon Fission Products in Reactor Coolant《用于反应堆冷却剂中氙裂变产物计算剂量当量疝 (DEX) 的.pdf
《ASTM D7727-2011e1 4379 Standard Practice for Calculation of Dose Equivalent Xenon &40 DEX&41 for Radioactive Xenon Fission Products in Reactor Coolant《用于反应堆冷却剂中氙裂变产物计算剂量当量疝 (DEX) 的.pdf》由会员分享,可在线阅读,更多相关《ASTM D7727-2011e1 4379 Standard Practice for Calculation of Dose Equivalent Xenon &40 DEX&41 for Radioactive Xenon Fission Products in Reactor Coolant《用于反应堆冷却剂中氙裂变产物计算剂量当量疝 (DEX) 的.pdf(3页珍藏版)》请在麦多课文档分享上搜索。
1、Designation: D7727 111Standard 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 adoption or, in the
2、 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.1NOTEEditorial corrections made throughout in March 2014.1. Scope1.1 This practice applies to the c
3、alculation of the doseequivalent to133Xe 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
4、that are provided for information onlyand 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
5、 applica-bility of regulatory limitations 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-
6、EQUIVALENT XE-133 (DEX), nshall be that133Xe 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
7、 general definition of DEX.Each utility 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. Summ
8、ary of Practice4.1 A sample of fresh reactor 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
9、 calculating the reactorcoolant calculation 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
10、 dose consequence analy-ses which form their 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
11、for radioactive releases.5. Significance 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 ac
12、tivity for a condition of 1 % fuel defects, 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 i
13、s performed in a similarmanner to that 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.
14、5.3 It is important to note that only fission gases areincluded in this calculation, and only the ones noted in Table 1.1This practice is under the jurisdiction of ASTM Committee D19 on Water andis the direct responsibility of Subcommittee D19.04 on Methods of RadiochemicalAnalysis.Current edition a
15、pproved May 15, 2011. Published June 2011. DOI: 10.1520/D7727-11E01.2For referenced ASTM standards, visit 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 w
16、ebsite.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States1For example83mKr is not included even though its half life is1.86 hours. The reason for this is that this radionuclide cannotbe easily determined by gamma spectrometry (low energy
17、X-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 this calculation.5.5 If a specific noble-gas radi
18、onuclide 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 GuidanceReport No. 12 (1),3or the average gamma-
19、disintegrationenergies as provided in ICRP Publication 38 (“RadionuclideTransformations”) or similar source.6. Interferences6.1 The analytical determination of the radionuclides usedfor this calculation is made by gamma ray spectrometry.Commercially available software is generally used to performthe
20、 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 radionuclide in order to determine accuratelythe activit
- 1.请仔细阅读文档,确保文档完整性,对于不预览、不比对内容而直接下载带来的问题本站不予受理。
- 2.下载的文档,不会出现我们的网址水印。
- 3、该文档所得收入(下载+内容+预览)归上传者、原创作者;如果您是本文档原作者,请点此认领!既往收益都归您。
下载文档到电脑,查找使用更方便
5000 积分 0人已下载
下载 | 加入VIP,交流精品资源 |
- 配套讲稿:
如PPT文件的首页显示word图标,表示该PPT已包含配套word讲稿。双击word图标可打开word文档。
- 特殊限制:
部分文档作品中含有的国旗、国徽等图片,仅作为作品整体效果示例展示,禁止商用。设计者仅对作品中独创性部分享有著作权。
- 关 键 词:
- ASTMD77272011E14379STANDARDPRACTICEFORCALCULATIONOFDOSEEQUIVALENTXENON40DEX41FORRADIOACTIVEXENONFISSIONPRODUCTSINREACTORCOOLANT

链接地址:http://www.mydoc123.com/p-526198.html