ASTM C1075-2017 Standard Practices for Sampling Uranium-Ore Concentrate《用于铀矿石浓缩物取样的标准实施规程》.pdf
《ASTM C1075-2017 Standard Practices for Sampling Uranium-Ore Concentrate《用于铀矿石浓缩物取样的标准实施规程》.pdf》由会员分享,可在线阅读,更多相关《ASTM C1075-2017 Standard Practices for Sampling Uranium-Ore Concentrate《用于铀矿石浓缩物取样的标准实施规程》.pdf(11页珍藏版)》请在麦多课文档分享上搜索。
1、Designation: C1075 10C1075 17Standard Practices forSampling Uranium-Ore Concentrate1This standard is issued under the fixed designation C1075; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of last revision. A number in p
2、arentheses indicates the year of last reapproval. Asuperscript epsilon () indicates an editorial change since the last revision or reapproval.1. Scope1.1 These practices are intended to provide the nuclear industry with procedures for obtaining representative bulk samples fromuranium-ore concentrate
3、s (UOC) (see Specification C967).1.2 These practices also provide for obtaining a series of representative secondary samples from the original bulk sample forthe determination of moisture and other test purposes, and for the preparation of pulverized analytical samples (see Test MethodsC1022 and C18
4、43).1.3 These practices consist of a number of alternative procedures for sampling and sample preparation which have been shownto be satisfactory through long experience in the nuclear industry. These procedures are described in the following order.Stage Procedure SectionPrimary Sampling One-stage f
5、alling stream 4Primary Sampling One-stage falling stream 5Two-stage falling stream 5Two-stage falling stream 6Auger 6Auger 7Secondary Sampling Straight-path (reciprocating) 7Secondary Sampling Straight-path (reciprocating) 8Rotating (Vezin) 8, 9Rotating (Vezin) 9, 10Sample Preparation 10Concurrent-d
6、rying 11 13Natural moisture 14 16Calcination 17, 18Sample Packaging 19Wax sealing 20Vacuum sealing 211.3.1 The primary and secondary sampling stages can be organized in the following way:1.3.2 It is possible to combine the various elements of these stages in different ways to give satisfactory resul
7、ts depending onthe agreed requirements of the contracting parties. For a given stage, however, each procedure must be regarded as a whole. It ishighly inadvisable to mix elements belonging to different procedures.1.4 These procedures do not include requirements for health, safety, and accountability
8、. The observance of these practices doesnot relieve the user of the obligation to be aware of and to conform to all applicable international, federal, state, and localregulations pertaining to processing, shipping, or using uranium-ore concentrates. (Guidance is provided in CFR 10, Chapter 1.)1.5 Th
9、e values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.1 These practices are under the jurisdiction ofASTM Committee C26 on Nuclear Fuel Cycle and are the direct responsibility of Subcommittee C26.02 on Fuel and FertileMaterial Specif
10、ications.Current edition approved Jan. 1, 2010Nov. 1, 2017. Published February 2010November 2017. Originally approved in 1986. Last previous edition approved in 20042010as C1075 93 (2004).C1075 10. DOI: 10.1520/C1075-10.10.1520/C1075-17.This document is not an ASTM standard and is intended only to p
11、rovide 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 prior editions as appropriate. In all cases only the current versionof t
12、he 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 States11.6 This standard does not purport to address all of the safety problems, if any, associated with its use. It i
13、s the responsibilityof the user of this standard to establish appropriate safety safety, health, and healthenvironmental practices and determine theapplicability of regulatory limitations prior to use.1.7 This international standard was developed in accordance with internationally recognized princip
14、les on standardizationestablished in the Decision on Principles for the Development of International Standards, Guides and Recommendations issuedby the World Trade Organization Technical Barriers to Trade (TBT) Committee.2. Referenced Documents2.1 ASTM Standards:2C859 Terminology Relating to Nuclear
15、 MaterialsC967 Specification for Uranium Ore ConcentrateC1022 Test Methods for Chemical and Atomic Absorption Analysis of Uranium-Ore ConcentrateC1843 Test Method for Determining Moisture Content in Uranium-Ore Concentrate2.2 Other Document:CFR 10 Nuclear Materials Licensing Code of Federal Regulati
16、ons, Chapter 133. Terminology3.1 Except as otherwise defined herein, definitions of terms are as given in Terminology C859.4. General Requirements4.1 Material Requirements:4.1.1 The uranium-ore concentrates shall be free-flowing and of a particle size not to exceed 6 mm (0.25 in.) or such other limi
17、tagreed upon between contracting parties.4.1.2 The average moisture content shall not exceed 5.0 % weight of the uranium-ore concentrates.4.1.3 The material shall be shipped to the sampling plant in 200-L (55-gal) standard steel drums that are fitted with steel lidsand equipped with suitable gasket,
18、 sealing rings, and sealing bungs (if applicable) to ensure weatherproofing. The drums shall beconstructed so that the top of the drum is fully open when the lid is removed.4.1.4 The number of drums in a sampling lot shall not exceed 90 and the gross weight shall not exceed 45 metric tons (100 000lb
19、).4.1.5 A minimum number of drums in a sampling lot may be established depending upon the sampling procedure used.4.2 Sampling Equipment Requirements:4.2.1 Care shall be taken in the design and operation of the sampling and all associated equipment to minimize the exchangesof air between the atmosph
20、ere and the sampling system. For obvious safety reasons dust-carrying internal air must be preventedfrom escaping the system. This is achieved by means of dust collectors. The latter, however, shall be designed and operated in sucha way that a minimum amount of external air shall be allowed into the
21、 system. The purpose of this is (1) to limit the exchangesof moisture between the atmosphere and the UOC and (2) to prevent a size-selective dusting. In any case, the amount of dustescaping the sampling operations must be kept to a minimum.4.2.2 The scales for the gross and tare weights of the drums
22、 shall be capable of reading to the nearest 0.2 kg (0.5 lb) and shallbe fitted with a print-out or data processing system, or both. They shall have a capacity of 600 kg (1300 lb). The weigh scale shallbe calibrated and adjusted if required, at the beginning, middle, and end of each lot weighed. Test
23、 weights shall be certified by astatutory authority and shall be traceable to national or state standards.4.2.3 All sampling containers shall be clean and dry before usage.5. Primary Sampling, Falling Stream1 % In One Stage5.1 ScopeThe falling-stream procedure provides for removing a large number of
24、 increments of the material as it falls freelyat a uniform, controlled rate. All of the material in a lot passes through the system and is subject to incremental sampling.5.2 Sampling Equipment Requirements:5.2.1 Aschematic diagram of a typical falling-stream sampling facility is shown in Fig. 1. Su
- 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
10000 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:
- ASTMC10752017STANDARDPRACTICESFORSAMPLINGURANIUMORECONCENTRATE 用于 铀矿 浓缩物 取样 标准 实施 规程 PDF

链接地址:http://www.mydoc123.com/p-463251.html