F40 核材料、核燃料综合 标准查询与下载

ISO 921:1997 核能 词汇 三种语言版

Gives terms and definitions in English, French and Russian used in the field of nuclear energy. The entry is in accordance with ISO 10241:1992

Nuclear energy - Vocabulary

ASTM C1285-97 确定核废物和混合废弃玻璃耐化学性能的标准试验方法:产品一致性试验(PCT)

1.1 These product consistency test methods A and B evaluate the chemical durability of homogeneous and devitrified glasses by measuring the concentrations of the chemical species released from a crushed glass to a test solution. 1.1.1 Test Method A is a seven-day crushed glass durability test performed at 90 + 2176C in a leachant of ASTM-Type I water. The test method is static and conducted in stainless steel vessels. Test Method A can specifically be used to evaluate whether the durability and elemental release characteristics of waste glasses have been consistently controlled during production. This test method is applicable to radioactive and simulated waste glasses. 1.1.2 Test Method B is a crushed glass durability test that allows testing of water glasses at varying test durations, test temperatures, ratios of glass surface area ( ) to leachant volume ( ), and leachant types. This test method is static and can be conducted in stainless steel or PFA TFE-fluorocarbon vessels, or both. Test Method B can specifically be used to evaluate the relative durability characteristics of homogeneous or devitrified glasses, or both. This test method is applicable to radioactive and simulated waste glasses. Test Method B cannot be used as a consistency test for production of high level radioactive waste glass. 1.2 These test methods must be performed in accordance with all quality assurance requirements for acceptance of the data. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses: The Product Consistency Test (PCT)

ANSI N14.5-1997 放射性原料.运输包装件泄露试验

Presents information leakage tests on packages for shipment.

Radioactive Materials - Leakage Tests on Packages for Shipment

EJ/T 1028-1996 锆-锡合金包壳燃料棒焊区腐蚀试验

Corrosion testing for welding zone of Zirconium-Tin alloys cladding fuel rad

ISO 9894:1996 六氟化铀液化分样

Describes a method of subsampling suitable for taking aliquots from a representative sample of uranium hexafluoride in the liquid phase. The subsamples are intended for isotopic analysis (1 g bis 3 g), impurity analysis (10 g bis 200 g) and uranium assay (5 g bis 10 g). Carbon halides, hydrocarbons and certain metal halides can be measured directly from the sample.

Subsampling of uranium hexafluoride in the liquid phase

EJ/T 1017-1996 核燃料循环中核材料取样通则

General principles for sampling nuclear material in the nuclear fuel cycle

ASTM C1343-96 用X线荧光测定油和有机溶液中铀的低浓度的标准试验方法

1.1 This test method covers the steps necessary for the preparation and analysis by X-ray fluorescence (XRF) of oils and organic solutions containing uranium.1.2 The procedure is valid for those solutions containing 20 to 2000 956;g uranium/mL as presented to the spectrometer.1.3 This test method requires the use of an appropriate internal standard. Care must be taken to ascertain that samples analyzed by this test method do not contain the internal standard or that this contamination, whenever present, has been corrected for mathematically. Such corrections are not addressed in this procedure. Care must be taken that the internal standard and sample medium are compatible; that is, samples must be miscible with tri-n-butyl phosphate (TBP) and must not remove the internal standard from solution. Alternatively, a scatter line may be used as the internal standard.1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. Specific precautionary statements are given in Section 9 and Note 2.

Standard Test Method for Determination of Low Concentrations of Uranium in Oils and Organic Liquids by X-Ray Fluorescence

ASTM C1346-96 P-10管中UF₆溶解性的标准实施规程

1.1 This practice covers the dissolution of UF 6 from a P-10 tube to provide solutions for analysis.1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. For specific safeguard and safety precaution statements, see Section 8.

Standard Practice for Dissolution of UF₆ from P-10 Tubes

ASTM C1343-96(2002) 用X线荧光测定油和有机溶液中铀的低浓度的标准试验方法

1.1 This test method covers the steps necessary for the preparation and analysis by X-ray fluorescence (XRF) of oils and organic solutions containing uranium.1.2 The procedure is valid for those solutions containing 20 to 2000 g uranium/mL as presented to the spectrometer.1.3 This test method requires the use of an appropriate internal standard. Care must be taken to ascertain that samples analyzed by this test method do not contain the internal standard or that this contamination, whenever present, has been corrected for mathematically. Such corrections are not addressed in this procedure. Care must be taken that the internal standard and sample medium are compatible; that is, samples must be miscible with tri-n-butyl phosphate (TBP) and must not remove the internal standard from solution. Alternatively, a scatter line may be used as the internal standard.1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. Specific precautionary statements are given in Section 9 and Note 2.

Standard Test Method for Determination of Low Concentrations of Uranium in Oils and Organic Liquids by X-ray Fluorescence

ASTM E393-96 通过分析由裂变剂量计产生的钡140来测定反应速率的试验方法

1.1 This test method describes two procedures for the measurement of reaction rates by determining the amount of the fission product Ba produced by the non-threshold reactions 235 U (n, f), 241 Am (n, f), and 239 Pu (n, f), and by the threshold reactions 238 U (n, f), 237 Np (n, f), and 232 Th (n, f). 1.2 These reactions produce many fission products, among which is 140 Ba, having a half-life of 12.752 days. 140 Ba emits gamma rays of several energies; however, these are not easily detected in the presence of other fission products. Competing activity from other fission products requires that a chemical separation be employed or that the Ba activity be determined indirectly by counting its daughter product La. This test method describes both procedure (a), the nondestructive determination of Ba by the direct counting of La several days after irradiation, and procedure (b), the chemical separation of Ba and the subsequent counting of Ba or its daughter 140 La. 1.3 With suitable techniques, fission neutron fluence rates can be measured in the range from 10 n (neutrons) [dot]cm -2 [dot]s -1 to approximately 10 15 n[dot]cm -2 [dot]s -1 . 1.4 The measurement of time-integrated reaction rates with fission dosimeters by Ba analysis is limited by the half-life of 140 Ba to irradiation times up to about six weeks. 1.5 The values stated in SI units are to be regarded as standard. 1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters

ASTM E393-96(2002) 通过分析由裂变剂量计产生的钡140来测定反应速率的试验方法

1.1 This test method describes two procedures for the measurement of reaction rates by determining the amount of the fission product 140Ba produced by the non-threshold reactions 235U (n, f), 241Am (n, f), and 239Pu (n, f), and by the threshold reactions 238U (n, f), 237Np (n, f), and 232Th (n, f).1.2 These reactions produce many fission products, among which is 140Ba, having a half-life of 12.752 days. 140Ba emits gamma rays of several energies; however, these are not easily detected in the presence of other fission products. Competing activity from other fission products requires that a chemical separation be employed or that the 140Ba activity be determined indirectly by counting its daughter product 140La. This test method describes both procedure (a), the nondestructive determination of 140Ba by the direct counting of 140La several days after irradiation, and procedure (b), the chemical separation of 140Ba and the subsequent counting of 140Ba or its daughter 140La.1.3 With suitable techniques, fission neutron fluence rates can be measured in the range from 107 n (neutrons) cm2 s1 to approximately 10 15 n cm2 s1.1.4 The measurement of time-integrated reaction rates with fission dosimeters by 140Ba analysis is limited by the half-life of 140Ba to irradiation times up to about six weeks.1.5 The values stated in SI units are to be regarded as standard.1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters

ASTM C1348-96 直接氢还原成核级二氧化铀用带低于5%的235U含量的混合氧化铀用标准规范

1.1 This specification covers blended uranium trioxide (UO3), U3O8, or mixtures of the two, powders that are intended for conversion into a sinterable uranium dioxide (UO2) powder by means of a direction reduction process. The UO2 powder product of the reduction process must meet the requirements of Specification C753 and be suitable for subsequent UO2 pellet fabrication by pressing and sintering methods. This specification applies to uranium oxides with a 235U enrichment less than 5 %. 1.2 This specification includes chemical, physical, and test method requirements for uranium oxide powders as they relate to the suitability of the powder for storage, transportation, and direct reduction of UO2 powder. This specification is applicable to uranium oxide powders for such use from any source. 1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all international, national, state, and local regulations for processing, shipping, or any other way of using uranium oxide powders (see 2.2 and 2.3). 1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. 1.5 The following safety hazards caveat pertains only to the test methods portion of the annexes in this specification: This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Specification for Blended Uranium Oxides with a ²³⁵U Content of Less Than 5 % for Direct Hydrogen Reduction to Nuclear Grade Uranium Dioxide

EJ/T 957-1995 压水堆燃料组件清洁度及清洗技术条件

本标准规定了压水堆燃料组件的清洁度和清洗工艺的要求。 本标准适用于压水堆燃料组件及其零部件的清洗，也适用于燃料相关组件的零部件清洗。

PWR Fuel Assembly Cleanliness and Cleaning Technical Conditions

EJ/T 946-1995 天然四氟化铀衡算交接规定

Provisions on Accounting and Handover of Natural Uranium Tetrafluoride

ASTM C1316-95 使用a252Cf的被动-主动中子计数法在碎片和废料中作核材料无损检定的标准试验方法

1.1 This test method covers the nondestructive assay of scrap and waste for uranium and plutonium content using a 252Cf shuffler. Shuffler measurements provide rapid results and can be applied to a variety of matrix materials in containers as large as 208-litre drums. Corrections are made for the effects of matrix material. This test method has been used to assay items containing uranium, plutonium, or both. Applications of this test method include measurements for safeguards, accountability, TRU, and U waste segregation, disposal, and process control purposes (1,2,3).1.1.1 This test method uses passive neutron coincidence counting to measure 238Pu, 240Pu, and 242Pu. It has been used to assay items with plutonium contents between 0.03 g and 1000 g. It could be used to measure other spontaneously fissioning isotopes. It specifically describes the approach used with shift register electronics; however, it can be adapted to other electronics. 1.1.2 This test method uses neutron irradiation with a moveable californium source and counting of the delayed neutrons from the induced fissions to measure 235U. It has been used to assay items with 235U contents between 0.1 g and 1000 g. It could be used to assay other fissionable isotopes.1.2 This test method requires knowledge of the relative isotopic composition to determine the mass of the different elements.1.3 This test method may give biased results for measurements of containers that include large quantities of hydrogen.1.4 The techniques described in this test method have been applied to materials other than scrap and waste. These other applications are not addressed in this test method.1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. Specific precautionary statements are given in Section 8.

Standard Test Method for Nondestructive Assay of Nuclear Material in Scrap and Waste by Passive-Active Neutron Counting Using a 252 Cf Shuffler

ASTM C1128-95e1 核燃料循环材料分析用操作参考材料制备的标准指南

1.1 This guide covers the preparation and characterization of working reference materials (WRM) that are produced by a laboratory for its own use in the analysis of nuclear materials. Guidance is provided for establishing traceability of WRMs to certified reference materials by a defined characterization process. The guidance provided is generic; it is not specific for a given material.1.2 The information provided by this guide is found in the following sections:SectionPlanning6Preparation7Packaging and Storage8Characterization9Statistical Analysis10Documentation 111.3 The values stated in SI units are to be regarded as the standard.1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Preparation of Working Reference Materials for Use in the Analysis of Nuclear Fuel Cycle Materials

ASTM C1307-95 用(III)钚数组分光光度法鉴定钚的标准测试方法

1.1 This test method describes the determination of total plutonium as plutonium(III) in nitrate and chloride solutions. The technique is applicable to solutions of plutonium dioxide powders and pellets (Test Methods C 697), nuclear grade mixed oxides (Test Methods C 698), plutonium metal (Test Methods C 758), and plutonium nitrate solutions (Test Methods C 759). Solid samples are dissolved using the appropriate dissolution techniques described in Practice C 1168. The use of this technique for other plutonium-bearing materials has been reported (1-5), but final determination of applicability must be made by the user. The applicable concentration range for plutonium sample solutions is 10-200 g Pu/L.1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Plutonium Assay by Plutonium (III) Diode Array Spectrophotometry

EJ/T 911-1994 U₃Si₂中硅的测定容量法

Volumetric Method for Determination of Silicon in U₃Si₂

EJ/T 897-1994 二氧化铀芯块中总气体量的测定

Determination of total gas content in uranium dioxide pellets

EJ/T 912-1994 U₃Si₂-Al板型燃料组件制造的质量控制

Quality Control of Manufacture of U₃Si₂-Al Plate Type Fuel Assembly