ASTM C1682-2017 Standard Guide for Characterization of Spent Nuclear Fuel in Support of Interim Storage Transportation and Geologic Repository Disposal《支持临池储存 运输和地质库处置的废核燃料特性描述的标准指.pdf
《ASTM C1682-2017 Standard Guide for Characterization of Spent Nuclear Fuel in Support of Interim Storage Transportation and Geologic Repository Disposal《支持临池储存 运输和地质库处置的废核燃料特性描述的标准指.pdf》由会员分享,可在线阅读,更多相关《ASTM C1682-2017 Standard Guide for Characterization of Spent Nuclear Fuel in Support of Interim Storage Transportation and Geologic Repository Disposal《支持临池储存 运输和地质库处置的废核燃料特性描述的标准指.pdf(10页珍藏版)》请在麦多课文档分享上搜索。
1、Designation: C1682 09C1682 17Standard Guide forCharacterization of Spent Nuclear Fuel in Support of InterimStorage, Transportation and Geologic Repository Disposal1This standard is issued under the fixed designation C1682; the number immediately following the designation indicates the year oforigina
2、l adoption 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 guide provides guidance for the types and extent of testing t
3、hat would be involved in characterizing the physical andchemical nature of spent nuclear fuel (SNF) in support of its interim storage, transport, and disposal in a geologic repository. Thisguide applies primarily to commercial light water reactor (LWR) spent fuel and spent fuel from weapons producti
4、on, although theindividual tests/analyses may be used as applicable to other spent fuels such as those from research and test reactors. reactors andmixed oxide (MOX) spent fuel. The testing is designed to provide information that supports the design, safety analysis, andperformance assessment of a g
5、eologic repository for the ultimate disposal of the SNF.1.2 The testing described includes characterization of such physical attributes as physical appearance, weight, density,shape/geometry, degree, and type of SNF cladding damage. The testing described also includes the measurement/examination ofs
6、uch chemical attributes as radionuclide content, microstructure, and corrosion product content, and such environmental responsecharacteristics as drying rates, oxidation rates (in dry air, water vapor, and liquid water), ignition temperature, and dissolution/degradation rates. Not all of the charact
7、erization tests described herein must necessarily be performed for any given analysis ofSNF repository performance,performance for interim storage, transportation, or geological repository disposal, particularly in areaswhere an extensive body of literature already exists for the parameter of intere
8、st.interest in the specific service condition.1.3 It is assumed in formulating the SNF characterization activities in this guide that the SNF has been stored in an interimstorage facility at some time between reactor discharge and dry transport to the geologic a repository. The SNF may have beenstor
9、ed either wet (for example, a spent fuel pool), or dry (for example, an independent spent fuel storage installation (ISFSI), orboth, and that the manner of interim storage may affect the SNF characteristics.1.4 The values stated in SI units are to be regarded as standard. No other units of measureme
10、nt are included in this standard.1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibilityof the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatorylimitatio
11、ns prior to use.1.6 This international standard was developed in accordance with internationally recognized principles on standardizationestablished in the Decision on Principles for the Development of International Standards, Guides and Recommendations issuedby the World Trade Organization Technica
12、l Barriers to Trade (TBT) Committee.2. Referenced Documents2.1 ASTM Standards:2C170/C170M Test Method for Compressive Strength of Dimension StoneC696 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium DioxidePowders and PelletsC698 Test Methods for C
13、hemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides (U,Pu)O2)C859 Terminology Relating to Nuclear Materials1 This guide is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel and
14、HighLevel Waste.Current edition approved June 1, 2009July 1, 2017. Published July 2009August 2017. Originally approved in 2009. Last previous edition approved in 2009 as C1682 09.DOI: 10.1520/C1682-09.10.1520/C1682-17.2 For referencedASTM standards, visit theASTM website, www.astm.org, or contactAST
15、M Customer Service at serviceastm.org. For Annual Book of ASTM Standardsvolume information, refer to the standards Document Summary page on the ASTM website.This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made
16、 to the previous version. Becauseit may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current versionof the standard as published by ASTM is to be considered the official document.Copyr
17、ight ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States1C1174 Practice for Prediction of the Long-Term Behavior of Materials, Including Waste Forms, Used in Engineered BarrierSystems (EBS) for Geological Disposal of High-Level Radioactive WasteC13
18、80 Test Method for the Determination of Uranium Content and Isotopic Composition by Isotope Dilution MassSpectrometryC1413 Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by ThermalIonization Mass SpectrometryC1454 Guide for Pyrophoricity/Combustibil
19、ity Testing in Support of PyrophoricityAnalyses of Metallic Uranium Spent NuclearFuel (Withdrawn 2016)3C1553 Guide for Drying Behavior of Spent Nuclear FuelE170 Terminology Relating to Radiation Measurements and Dosimetry2.2 U.S. Government Documents4Code of Federal Regulations, Title 10, Part 60 Di
20、sposal of High-Level Radioactive Wastes in Geologic Repositories, U.S.Nuclear Regulatory Commission, January 1997CommissionCode of Federal Regulations, Title 10, Part 63 Disposal of High-Level Radioactive Wastes in a Geologic Repository at YuccaMountain, Nevada, U.S. Nuclear Regulatory CommissionCod
21、e of Federal Regulations, Title 10, Part 71 Packaging and Transport of Radioactive MaterialsCode of Federal Regulations, Title 10, Part 72 Licensing Requirements for the Independent Storage of Spent Nuclear Fuel andHigh-Level Radioactive WasteCode of Federal Regulations, Title 10, Part 961 Standard
22、contract for the Disposal of Spent Nuclear Fuel and/or High LevelWasteCode of Federal Regulations, Title 40, Part 191 Environmental Radiation Protection Standards for Management and Disposalof Spent Nuclear Fuel, High-Level and Transuranic Radioactive WastesCode of Federal Regulations Title 40, Part
23、 197 2005 Protection of Environment: Public Health and Environmental RadiationStandards for Yucca Mountain, Nevada3. Terminology3.1 DefinitionsDefinitions used in this guide are as currently existing in Terminology C859 or Test Method C170/C170M, oras commonly accepted in dictionaries of the English
24、 language, except for those terms defined below for the specific usage of thisstandard. For consistency, many of the definitions are based on definitions from Federal Regulations in the United States.3.2 Definitions of Terms Specific to This Standard:3.2.1 alteration, nany change to the form, state,
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