F40 核材料、核燃料综合 标准查询与下载

EJ/T 895-1994 六氟化铀的液化分样

Liquefaction of uranium hexafluoride

ISO 9006:1994 铀金属二氧化铀粉末和芯块 氮含量的测定 氨敏电极法

Specifies an analytical method for determining the nitrogen content in uranium metal and uranium dioxide powder and pellets. Applicable to the determination of nitrogen, present as nitride.

Uranium metal and uranium dioxide powder and pellets - Determination of nitrogen content - Method using ammonia-sensing electrode

ISO 11483:1994 钚源的制备以及利用α谱仪测量238Pu/239Pu同位素比值

Preparation of plutonium sources and determination of <(hoch)238>Pu/<(hoch)239>Pu isotope ratio by alpha spectrometry

ANSI N15.36-1994 核材料.无损检测测量的控制和保证

Nuclear materials - Nondestructive assay measurement control and assurance

ISO 11482:1993 核燃料后处理厂二氧化钚取样导则

Gives guidelines to ensure that the homogenization and the sampling system supply representative samples from a batch of plutonium dioxide and to ensure that the said sample remains representative until aliquoting. Possible mass change of the sample during transport and storage is also considered. The guidelines apply to PuO powder with a specific surface area lower than 25 m/g.

Guidelines for plutonium dioxide (PuO₂) sampling in a nuclear reprocessing plant

GOST 4.92-1993 放射性技术.指标项目

Настоящий стандарт распространяется на изделия радиационной техники: радионуклидные термоэлектрические генераторы, гамма-дефектоскопы,

Product quality index system. Radiation equipment. Nomenclature of indices

ASTM C1022-93 铀精矿的化学分析和原子吸收分析的标准试验方法

1.1 These test methods cover procedures for the chemical and atomic absorption analysis of uranium-ore concentrates to determine compliance with the requirements prescribed in Specification C 967.1.2 The analytical procedures appear in the following order:SectionsUranium by Ferrous Sulfate Reduction-Potassium Dichromate Titrimetry9Nitric Acid-Insoluble Uranium10 to 18Extractable Organic Material19 to 26Arsenic by Diethyldithiocarbamate (Photometric Method)27 to 36Carbonate by CO2 Gravimetry37 to 43Fluoride by Ion-Selective Electrode44 to 51Halides by Volhard Titration52 to 59Moisture by Loss of Weight at 110176;C60 to 66Phosphorus by Spectrophotometry67 to 75Silicon by Gravimetry76 to 82Thorium by the Thorin (Photometric) Method83 to 91Calcium, Iron, Magnesium, Molybdenum, Titanium, and Vana-dium by Atomic Absorption Spectrophotometry92 to 101Potassium and Sodium by Atomic Absorption Spectrophotometry102 to 111Boron by Spectrophotometry112 to 1211.3 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. Specific precautionary statements are given in Sections 7, 32, and Note 14.

Standard Test Methods for Chemical and Atomic Absorption Analysis of Uranium-Ore Concentrate

EJ/T 681-1992 核燃料后处理厂安全分析报告的标准格式与内容

Standard format and content of safety analysis report for nuclear fuel reprocessing plant

EJ 622-1992 反应堆燃料元件术语

本标准规定了反应堆燃料元件领域的技术术语和定义。 本标准适用于反应燃料元件领域的标准、技术文件、书刊、教材和手册等的编写和翻译。 本标准中方括号内的字为在不引起混淆情况下可省略的字，圆括号内为加注或替换词。本标准按汉语拼音字母顺序排列，英文索引见附录A（补充件）。

Reactor Fuel Element Terminology

ASTM C1204-91(1996) 在有钚存在的情况下经铬(VI)滴定后用磷酸中铁(II)量减少法测定铀的试验方法

1.1 This test method covers unirradiated uranium-plutonium mixed oxide having a uranium to plutonium ratio of 2.5 and greater. The presence of larger amounts of plutonium (Pu) that give lower uranium to plutonium ratios may give low analysis results for uranium (U) (1), if the amount of plutonium together with the uranium is sufficient to slow the reduction step and prevent complete reduction of the uranium in the allotted time. Use of this test method for lower uranium to plutonium ratios may be possible, especially when 20 to 50 mg quantities of uranium are being titrated rather than the 100 to 300 mg in the study cited in Ref (1). Confirmation of that information should be obtained before this test method is used for ratios of uranium to plutonium less than 2.5.1.2 The amount of uranium determined in the data presented in Section was 20 to 50 mg. However, this test method, as stated, contains iron in excess of that needed to reduce the combined quantities of uranium and plutonium in a solution containing 300 mg of uranium with uranium to plutonium ratios greater than or equal to 2.5. Solutions containing up to 300 mg uranium with uranium to plutonium ratios greater than or equal to 2.5 have been analyzed (1) using the reagent volumes and conditions as described in Section 10.1.3 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. For specific hazard statements, see Section 8.

Standard Test Method for Uranium in the Presence of Plutonium by Iron(II) Reduction in Phosphoric Acid Followed by Chromium(VI) Titration

ASTM C1206-91(1996) 铁(II)/铬(VI)安培计滴定法测定钚的试验方法

1.1 This test method covers the determination of plutonium in unirradiated nuclear-grade plutonium dioxide, uranium-plutonium mixed oxides with uranium (U)/plutonium (Pu) ratios up to 21, plutonium metal, and plutonium nitrate solutions. Optimum quantities of plutonium to measure are 7 to 15 mg.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 by Iron (II)/Chromium (VI) Amperometric Titration

ANSI N15.51-1990 核材料管理.测量控制计划.核材料分析化学实验室

This standard provides the principal elements of a measurement control program for an analytical chemistry laboratory supporting nuclear fuel cycle activities. The ability to safely manage and to maintain accounts of these materials requires measurement of the materials as they are produced, used, shipped, stored, and inventoried. A comprehensive measurement control program demonstrates the reliability of the measurement data, quantifies the performance of the measurement system, assures that the measurements used in the nuclear industry are suitable for their intended use, and provides for detection and correction of adverse changes.

Measurement Control Program - Nuclear Materials Analytical Chemistry Laboratory

ASTM E385-90(2002) 使用14兆电子伏特的中子活化和直接计数技术测定含氧量的试验方法

1.1 This test method covers the measurement of oxygen concentration in almost any matrix by using a 14-MeV neutron activation and direct-counting technique. Essentially, the same system may be used to determine oxygen concentrations ranging from over 50 % to about 10 956;g/g, or less, depending on the sample size and available 14-MeV neutron fluence rates. Note 18212;The range of analysis may be extended by using higher neutron fluence rates, larger samples, and higher counting efficiency detectors.1.2 This test method may be used on either solid or liquid samples, provided that they can be made to conform in size, shape, and macroscopic density during irradiation and counting to a standard sample of known oxygen content. Several variants of this method have been described in the technical literature. A monograph is available which provides a comprehensive description of the principles of activation analysis using a neutron generator (1).1.3 The values stated in either SI or inch-pound units are to be regarded separately as the standard. The values given in parentheses are for information only.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. Specific precautions are given in Section 8.

Standard Test Method for Oxygen Content Using a 14-MeV Neutron Activation and Direct-Counting Technique

EJ/T 362-1989 核燃料化学分析方法标准编写通则

General rules for preparation of standards for nuclear fuel chemical analysis methods

ARMY MIL-C-48665-1986 环形核

This specification contain requirements not normally covered by drawings and provide qualityas surance provision for the core, toroid for use on Mine, AT, in the FASCAM Systems.

CORE; TOROID

ISO 921:1972/Add 1:1980 第1次补充

Addendum 1-1980

ISO 921:1972 核能词汇.三种语言版

Nuclear energy glossary Trilingual edition

ARMY MIL-R-51060-1961 BETA.M6锶-90钇放射性试样

This specification covers one type of radioactive source for use in radiac calibrating instruments.

RADIOACTIVE TEST SAMPLE, STRONTIUM 90-YTTRIUM 90, BETA, M6

ARMY MIL-R-14588-1957 放射性试样(COBALT 60.M1)

This specification covers one type of radioactive source t o be used(in conjunction with a reniote handling device) as a portable source of gamma radiatif for training in radiation measuring and monitoring techniques, and for calibraty: of training type radiac instruments in the field.

RADIOACTIVE TEST SAMPLE (COBALT 60, M1)