27.120.30 裂变物质 标准查询与下载

OENORM EN ISO 18256-2:2021 核燃料技术 含二氧化钚材料的溶解 第2部分：MOX 球团和粉末的溶解（ISO 18256-2:2019）

Nuclear fuel technology - Dissolution of plutonium dioxide-containing materials - Part 2: Dissolution of MOX pellets and powders (ISO 18256-2:2019)

OENORM EN ISO 8299:2021 核燃料技术 通过热电离质谱法测定硝酸溶液中核材料的同位素和元素铀和钚浓度（ISO 8299:2019）

Nuclear fuel technology - Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry (ISO 8299:2019)

OENORM EN ISO 9161:2021 二氧化铀粉末-表观密度和振实密度的测定（ISO 9161:2019）

Uranium dioxide powder - Determination of apparent density and tap density (ISO 9161:2019)

BS EN ISO 18256-1:2021 核燃料技术 含二氧化钚材料的溶解 二氧化钚粉末的溶解

1   Scope This document specifies the dissolution of powder samples of plutonium oxide for subsequent determination of elemental concentration and isotopic composition.

Nuclear fuel technology. Dissolution of plutonium dioxide-containing materials - Dissolution of plutonium dioxide powders

BS EN ISO 9463:2021 核能 核燃料技术 分光光度法测定硝酸溶液中的钚

1   Scope This document specifies an analytical method by spectrophotometry, for determining the plutonium concentration in nitric acid solutions, with spectrophotometer implemented in hot cell and glove box allowing the analysis of high activity solutions. Commonly, the method is applicable, without interference, even in the presence of numerous cations, for a plutonium concentration higher than 0,5 mg·l −1 in the original sample with a standard uncertainty, with coverage factor k  = 1, less than 5 %. The method is intended for process controls at the different steps of the process in a nuclear fuel reprocessing plant or in other nuclear facilities.

Nuclear energy. Nuclear fuel technology. Determination of plutonium in nitric acid solutions by spectrophotometry

BS EN ISO 16793:2021 核燃料技术 用于微观结构检查的 UO2 烧结球团陶瓷照相制备指南

1   Scope This document describes the ceramographic preparation of uranium dioxide (UO 2 ) sintered pellets for qualitative and quantitative microstructure examinations. These examinations can be carried out before and after thermal or chemical etching. They enable — observations of fissures, inter- or intra-granular pores and inclusions, and — measurement of pore and grain size and measurement of pore and grain size distributions. The measurement of average grain size can be carried out using a classical counting method as described in ISO 2624 or ASTM E112 [ 3 ] , i.e. intercept procedure, comparison with standard grids or reference photographs. The measurement of pore-size distributions is usually carried out by an automatic image analyser. If the grain-size distributions are also measured with an image analyser, it is recommended that thermal etching be used to reveal the grain structure uniformly throughout the whole sample.

Nuclear fuel technology. Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination

BS EN ISO 9161:2021 二氧化铀粉末 表观密度和振实密度的测定

1   Scope This document specifies a method of determining the apparent density and tap density of free-flowing uranium dioxide (UO 2 ) powder which will be used for pelleting and sintering of UO 2 pellets as a nuclear fuel. This method can be used for different UO 2 powder types including grains, granules, spheres or other kinds of particles. The method can also be applied to other fuel powders as PuO 2 , ThO 2 and powder mixtures as UO 2 -PuO 2 and UO 2 -Gd 2 O 3 . This document is based on the principle of using a flowmeter funnel (see 4.1). Other measurement apparatus, such as a Scott volumeter, can also be used.

Uranium dioxide powder. Determination of apparent density and tap density

BS EN ISO 8299:2021 核燃料技术 热电离质谱法测定硝酸溶液中核材料的同位素和元素铀和钚浓度

1   Scope This document specifies a method for the determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry. The method applies to uranium and plutonium isotope composition and concentration measurement of irradiated Magnox and light water reactor fuels (boiling water reactor or pressurized water reactor), in final products at spent-fuel reprocessing plants, and in feed and products of MOX and uranium fuel fabrication. The method is applicable to other fuels, but the chemical separation and spike solution are, if necessary, adapted to suit each type of fuel.

Nuclear fuel technology. Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry

BS EN ISO 18256-2:2021 核燃料技术 含二氧化钚材料的溶解 MOX 颗粒和粉末的溶解

1   Scope This document specifies the dissolution of samples consisting of MOX pellets or powders to provide suitable aliquots for subsequent analysis of elemental concentration and isotopic composition.

Nuclear fuel technology. Dissolution of plutonium dioxide-containing materials - Dissolution of MOX pellets and powders

DS/EN ISO 9463:2021 核能—核燃料技术—分光光度法测定硝酸溶液中钚（ISO 9463:2019）

Nuclear energy – Nuclear fuel technology – Determination of plutonium in nitric acid solutions by spectrophotometry (ISO 9463:2019)

DS/EN ISO 18256-2:2021 核燃料技术《含二氧化钚材料的溶解》第2部分：MOX球团和粉末的溶解（ISO 18256-2:2019）

Nuclear fuel technology – Dissolution of plutonium dioxide-containing materials – Part 2: Dissolution of MOX pellets and powders (ISO 18256-2:2019)

DS/EN ISO 8299:2021 核燃料技术 用热电离质谱法测定硝酸溶液中核材料的同位素和元素铀和钚浓度（ISO 8299:2019）

Nuclear fuel technology – Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry (ISO 8299:2019)

DS/EN ISO 9161:2021 二氧化铀粉 表观密度和振实密度的测定（ISO 9161:2019）

Uranium dioxide powder – Determination of apparent density and tap density (ISO 9161:2019)

DS/EN ISO 16793:2021 核燃料技术 微观结构检查用 UO2 烧结球团的陶瓷制备指南（ISO 16793:2018）

Nuclear fuel technology – Guidelines for ceramographic preparation of UO₂ sintered pellets for microstructure examination (ISO 16793:2018)

DS/EN ISO 18256-1:2021 核燃料技术《含二氧化钚材料的溶解》第1部分：二氧化钚粉末的溶解（ISO 18256-1:2019）

Nuclear fuel technology – Dissolution of plutonium dioxide-containing materials – Part 1: Dissolution of plutonium dioxide powders (ISO 18256-1:2019)

ASTM C1307-21 钚（III）二极管阵列分光光度法钚测定的标准测试方法

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 resulting from plutonium dioxide powders and pellets (Test Methods C697), nuclear grade mixed oxides (Test Methods C6

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

DS/ISO 10276:2021 核能“燃料技术”用于运输放射性物质的包装的耳轴系统

Nuclear energy – Fuel technology – Trunnion systems for packages used to transport radioactive material

EN ISO 9161:2021 二氧化铀粉末.表观密度和抽头密度的测定

Uranium dioxide powder - Determination of apparent density and tap density (ISO 9161:2019)

EN ISO 18256-2:2021 溶解含钚二氧化物的材料 - 第2部分:MOX材料的溶解

Nuclear fuel technology - Dissolution of plutonium dioxide-containing materials - Part 2: Dissolution of MOX pellets and powders (ISO 18256-2:2019)

EN ISO 8299:2021 硝酸溶液中铀钚同位素含量和浓度的测定质谱法

Nuclear fuel technology - Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry (ISO 8299:2019)