ASTM C992-2011 Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks《核废料储存架用硼基中子吸收材料系统标准规格》.pdf
《ASTM C992-2011 Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks《核废料储存架用硼基中子吸收材料系统标准规格》.pdf》由会员分享,可在线阅读,更多相关《ASTM C992-2011 Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks《核废料储存架用硼基中子吸收材料系统标准规格》.pdf(5页珍藏版)》请在麦多课文档分享上搜索。
1、Designation:C99206 Designation: C992 11Standard Specification forBoron-Based Neutron Absorbing Material Systems for Usein Nuclear Spent Fuel Storage Racks1This standard is issued under the fixed designation C992; the number immediately following the designation indicates the year oforiginal adoption
2、 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 specification defines criteria for boron-based neutron absorbing materi
3、al systems used in racks in a pool environmentfor storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality inthe storage rack system.1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical co
4、mpound containingboron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials.1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron tothe extent of 18.3 6 0.2 % by weight (depending upon the
5、 geological origin of the boron). Boron, enriched in boron-10 could alsobe used.1.4 The materials systems described herein shall be functional that is always be capable to maintain a B10 areal density suchthat subcriticality Keff 0.95 or Keff 0.98 or Keff 1.0 depending on the design specification fo
6、r the service life (approximately40 years) in the operating environment of a nuclear spent fuel pool.1.5 A number of acceptable boron-based absorbing materials combinations are currently available while others are beingdeveloped for use in the future. This specification defines criteria essential an
7、d applicable to all materials combinations andidentifies parameters a buyer should specify to satisfy a unique or particular requirement.1.6 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents orrequirements for health and safety. Observ
8、ance of this specification does not relieve the user of the obligation to conform to allapplicable international, national, and local regulations.2. Referenced Documents2.1 ASTM Standards:2A240/A240M Specification for Chromium and Chromium-Nickel Stainless Steel Plate, Sheet, and Strip for Pressure
9、Vesselsand for General ApplicationsB209 Specification for Aluminum and Aluminum-Alloy Sheet and PlateC750 Specification for Nuclear-Grade Boron Carbide PowderC859 Terminology Relating to Nuclear MaterialsC1187 Guide for Establishing Surveillance Test Program for Boron-Based Neutron Absorbing Materia
10、l Systems for Use inNuclear Spent Fuel Storage RacksE105 Practice for Probability Sampling of MaterialsASTM Dictionary of Engineering Science and Technology2.2 ANSI Standards:3ANSI 45.2.2 Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power PlantsANSI-ASME NQA-1 Quality As
11、surance Requirements for Nuclear Facility Application2.3 U. S. Government Documents:4Title 10,10CFR50 Title 10, CFR, Energy Part 50 (10CFR50) Licensing of Production and Utilization FacilitiesTitle 10,10CFR72 Title 10, CFR, Energy Part 72 (10CFR72) Licensing Requirements for the Storage of Spent Fue
12、l in anIndependent Spent Fuel Storage Installation (ISFSI)1This specification is under the jurisdiction ofASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.03 on NeutronAbsorberMaterials Specifications.Current edition approved Feb. 15, 2006.1, 2011. Publis
13、hed March 2006.February 2011. Originally approved in 1983. Last previous edition approved in 19972006 asC99289(1997).C992 06. DOI: 10.1520/C0992-06.10.1520/C0992-11.2For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at serviceastm.org. For Annual Book
14、 of ASTM Standardsvolume information, refer to the standards Document Summary page on the ASTM website.3Available from the American National Standards Institute, 11 W. 42nd St., 13th Floor, New York, NY 10036.4Available from Superintendent of Documents, U. S. Government Printing Office, Washington,
15、DC 20402.1This 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 to the previous version. Becauseit may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult
16、 prior editions as appropriate. In all cases only the current versionof the standard as published by ASTM is to be considered the official document.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.3. Terminology3.1 Definitions of Terms
17、 Specific to This Standard:3.1.1 Terms shall be defined in accordance with Terminology C859 or the ASTM Dictionary of Engineering Science andTechnology, except as defined as follows:3.1.2 accelerated testinga procedure for investigating the potential for long-term changes in physical properties or c
18、hemicalcomposition of a material important to safety, caused by a system operating parameter such as temperature, chemical environmentor radiation.3.1.2.1 DiscussionThe procedure uses a value of the identified parameter that is outside the normal bound of the operatingparameter being investigated, i
19、n order to (1) increase the rate of degradation, if any, (2) identify the operating limit for acceptablelimit of the parameter, and (3) to provide information that might assist in interpreting the degradation mechanism(s) involved. Inthis manner, the long-term behavior of a material may be simulated
20、 in an appreciably shorter period of time.3.1.3 areal densitythe boron-10 per unit area of a sheet, which is equivalent to the mass per unit volume of boron-10 in thematerial multiplied by the thickness of the material in which that isotope is contained.3.1.4 buyerthe organization issuing the purcha
21、se order.3.1.5 individual piecea discrete section of neutron absorber material whose individual dimensions conform to those in thepurchase specification.3.1.6 irradiationthe incidence of neutron, gamma, and beta radiation from spent fuel assemblies on materials in a water-filledspent fuel pool.3.1.7
22、 production batcha group of neutron-absorbing material pieces produced in a continuous production period, all of whichcan be shown to have the same chemical composition, physical, and nuclear properties within specification limits.3.1.8 sellerthe neutron absorbing system manufacturer.3.1.9 service l
23、ifethe period of time for which properties of the neutron-absorbing material system are expected to remain incompliance with the contract requirements which relate to chemical and physical integrity.3.1.10 supplierany outside source of raw materials and services used by the seller.4. Ordering Inform
24、ation4.1 The buyer should specify a material for which there is documented evidence that the neutron absorbing material system iscapable of acceptable performance in the following environmental conditions to which the material is expected to be exposed:4.1.1Total service life of the neutron absorbin
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