ImageVerifierCode 换一换
格式:PDF , 页数:26 ,大小:333.88KB ,
资源ID:184568      下载积分:9 积分
快捷下载
登录下载
邮箱/手机:
温馨提示:
快捷下载时,用户名和密码都是您填写的邮箱或者手机号,方便查询和重复下载(系统自动生成)。 如填写123,账号就是123,密码也是123。
特别说明:
请自助下载,系统不会自动发送文件的哦; 如果您已付费,想二次下载,请登录后访问:我的下载记录
支付方式: 支付宝扫码支付 微信扫码支付   
验证码:   换一换

加入VIP,免费下载
 

温馨提示:由于个人手机设置不同,如果发现不能下载,请复制以下地址【https://www.wnwk.com/docdown/184568.html】到电脑端继续下载(重复下载不扣费)。

已注册用户请登录:
账号:
密码:
验证码:   换一换
  忘记密码?
三方登录: QQ登录  

下载须知

1: 本站所有资源如无特殊说明,都需要本地电脑安装OFFICE2007和PDF阅读器。
2: 试题试卷类文档,如果标题没有明确说明有答案则都视为没有答案,请知晓。
3: 文件的所有权益归上传用户所有。
4. 未经权益所有人同意不得将文件中的内容挪作商业或盈利用途。
5. 本站仅提供交流平台,并不能对任何下载内容负责。
6. 下载文件中如有侵权或不适当内容,请与我们联系,我们立即纠正。
7. 本站不保证下载资源的准确性、安全性和完整性, 同时也不承担用户因使用这些下载资源对自己和他人造成任何形式的伤害或损失。

版权提示 | 免责声明

本文(ASTM_C_1562_-_10.pdf)为本站会员(益****师)主动上传,蜗牛文库仅提供信息存储空间,仅对用户上传内容的表现方式做保护处理,对上载内容本身不做任何修改或编辑。 若此文所含内容侵犯了您的版权或隐私,请立即通知蜗牛文库(发送邮件至admin@wnwk.com或直接QQ联系客服),我们立即给予删除!

ASTM_C_1562_-_10.pdf

1、Designation:C156210Standard Guide forEvaluation of Materials Used in Extended Service of InterimSpent Nuclear Fuel Dry Storage Systems1This standard is issued under the fixed designation C1562;the number immediately following the designation indicates the year oforiginal adoption or,in the case of r

2、evision,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 Part of the total inventory of commercial spent nuclearfuel(SNF)is stored in dry cask storage systems(D

3、CSS)underlicenses granted by the U.S.Nuclear Regulatory Commission(NRC).The purpose of this guide is to provide information toassist in supporting the renewal of these licenses,safely andwithout removal of the SNF from its licensed confinement,forperiods beyond those governed by the term of the orig

4、inallicense.This guide provides information on materials behaviorunder conditions that may be important to safety evaluationsfor the extended service of the renewal period.This guide iswritten for DCSS containing light water reactor(LWR)fuelthat is clad in zirconium alloy material and stored in acco

5、r-dance with the Code of Federal Regulations(CFR),at anindependent spent-fuel storage installation(ISFSI).2The com-ponents of an ISFSI,addressed in this document,include thecommercial SNF,canister,cask,and all parts of the storageinstallation including the ISFSI pad.The language of this guideis base

6、d,in part,on the requirements for a dry SNF storagelicense that is granted,by the U.S.Nuclear Regulatory Com-mission(NRC),for up to 20 years.Although governmentregulations may differ for various nations,the guidance onmaterials properties and behavior given here is expected tohave broad applicabilit

7、y.1.2 This guide addresses many of the factors affecting thetime-dependent behavior of materials under ISFSI service 10CFR Part 72.42.These factors are those regarded to beimportant to performance,in license extension,beyond thecurrently licensed 20-year period.Examples of these factorsare given in

8、this guide and they include materials alterations orenvironmental conditions for components of an ISFSI systemthat,over time,could have significance related to safety.Forpurposes of this guide,a license period of an additional 20 to80 years is assumed.1.3 This guide addresses the determination of th

9、e conditionsof the spent fuel and storage cask materials at the end of theinitial 20-year license period as the result of normal events andconditions.However,the guide also addresses the analysis ofpotential spent fuel and cask materials degradation as the resultof off-normal,and accident-level even

10、ts and conditions thatmay occur during any period.1.4 This guide provides information on materials behaviorto support continuing compliance with the safety criteria,which are part of the regulatory basis,for licensed storage ofSNF at an ISFSI.The safety functions addressed and discussedin this stand

11、ard guide include thermal performance,radiologi-cal protection,confinement,sub-criticality,and retrievability.The regulatory basis includes 10 CFR Part 72 and supportingregulatory guides of the U.S.Nuclear Regulatory Commission.The requirements set forth in these documents indicate that thefollowing

12、 items were considered in the original licensingdecisions:properties of materials,design considerations fornormal and off-normal service,operational and natural events,and the bases for the original calculations.These items mayrequire reconsideration of the safety-related arguments thatdemonstrate h

13、ow the systems continue to satisfy the regulatoryrequirements.Further,to ensure continued safe operation,theperformance of materials must be justified in relation to theeffects of time,temperature,radiation field,and environmentalconditions of normal and off-normal service.Arguments forlong-term per

14、formance must account for materials alterations(especially degradations)that are expected during the serviceperiods,which include the periods of the initial license and ofthe license renewal.This guide pertains only to structures,systems,and components important to safety during extendedstorage peri

15、od and during retrieval functions,including trans-port and transfer operations.Materials information that per-tains to safety functions,including retrieval functions,ispertinent to current regulations and to license renewal process,and this information is the focus of the guide.This guide is notinte

16、nded to supplant the existing regulatory process.1This guide is under the jurisdiction of ASTM Committee C26 on Nuclear FuelCycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel andHigh Level Waste.Current edition approved Jan.1,2010.Published March 2010.Originallyapproved in 2003.Last previous edition approved in 2003 as C1562 032.DOI:10.1520/C1562-10.2In general fuels of higher burnup(45 MWd/kgU)and MOX fuels are notincluded in this guide.Guidance for these fuels are expe

copyright@ 2008-2023 wnwk.com网站版权所有

经营许可证编号:浙ICP备2024059924号-2