F40 核材料、核燃料综合 标准查询与下载

EJ/T 551-2018 区域铀矿资源潜力评价指南

Guidelines for Regional Uranium Resource Potential Evaluation

EJ/T 20155-2018 地浸砂岩型铀矿野外资料整理要求

Requirements for field data compilation of in-situ leaching sandstone-type uranium deposits

EJ/T 974-2018 铀矿区域地质调查规范（1∶50 000）

Specifications for Regional Geological Survey of Uranium Mine (1:50 000)

EJ/T 1009-2018 铀矿山矿坑涌水量计算规定

Rules for Calculation of Water Inflow in Pit of Uranium Mine

EJ/T 741-2018 铀矿山矿石放射性计量站设计规定

Regulations for the design of ore radioactivity measurement stations in uranium mines

EJ/T 20151-2018 硬岩型铀矿探采对比指南

Hard rock type uranium prospecting comparison guide

EJ/T 20154-2018 铀矿石中硫、总碳、有机碳及无机碳的测定 红外吸收法

Determination of sulfur, total carbon, organic carbon and inorganic carbon in uranium ore by infrared absorption method

EJ/T 1070-2018 铀矿岩矿心管理规定

Management stipulation of uranium drilling core

EJ/T 20138.5-2018 硬岩型铀矿地质图件编制规定 第5部分：水文地质图、钻孔抽水试验综合成果图

Regulations for Compilation of Geological Maps of Hard Rock Uranium Deposits Part 5: Hydrogeological Maps and Comprehensive Result Maps of Drilling and Pumping Tests

EJ/T 20182-2018 铀资源调查航空高光谱数据处理技术要求

Technical requirements for aerial hyperspectral data processing of uranium resources investigation

EJ/T 1157-2018 地浸砂岩型铀矿地质勘查规范

Exploration specifications on in-situ leaching sandstone type uranium deposits

EJ/T 969-2018 铀矿区域地质调查规范（1∶250 000）

Specifications for Regional Geological Survey of Uranium Mine (1:250 000)

EJ/T 299-2018 硬岩型铀矿水文地质勘查规范

Specifications for Hydrogeological Exploration of Hard Rock Uranium Deposits

ASTM C1868-18 微观结构分析用UO2和混合氧化物(U, Pu)O2芯块的磁相制备的标准实施规程

5.1 The ceramographic examination of the nuclear fuel pellet is mandatory to ensure that the microstructural characteristics are in compliance with the fuel specifications relative to performance in reactor, particularly concerning thermo-mechanical behavior and fission gas release. 5.2 This practice is applicable for sintered UO2 pellets with any 235U concentration and (U,Pu)O2 pellets containing up to 15 weight % PuO2 with less than 108201;% porosity. 1.1 This practice describes the procedure for preparing nuclear-grade uranium dioxide (UO2) or mixed uranium-plutonium dioxide (MOX or (U,Pu)O2)), sintered and non-irradiated pellets for subsequent microstructural analysis (hereafter referred to as ceramographic examination). 1.2 The ceramographic examination is performed to confirm that the microstructure of the sintered pellet is in compliance with the fuel specification, for example as defined in Specifications C776 and C833, as a function of the initial raw material properties and manufacturing process parameters. 1.3 The microstructure of a ceramic pellet includes: grain size, porosity size and distribution, and phase distribution for (U,Pu)O2 pellets, that is, Pu-rich cluster size and distribution.2 1.4 The microstructural characteristics of the pellet are accessible after preparation which involves: sawing, mounting in a resin, surface polishing, and chemical etching, thermal etching, or both. 1.5 This practice describes the preparation processes mentioned in 1.4; it does not discuss the associated sampling practices (for example, Practice E105) or ceramographic examination methods (for example, the methods for determining average grain size are covered in Test Method E112). 1.6 Due to the radiotoxicity associated with these nuclear materials, all operations described in this practice should be performed in glovebox for (U,Pu)O2 pellets and in a hood for UO2 pellets. 1.7 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.8 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, health, and environmental practices and determine the applicabilit......

Standard Practice for Ceramographic Preparation of UO2 and Mixed Oxide (U,Pu)O2 Pellets for Microstructural Analysis

BS ISO 12800:2017 核燃料技术. 采用BET法测量氧化铀粉末特定表面面积的指南

Nuclear fuel technology. Guidelines on the measurement of the specific surface area of uranium oxide powders by the BET method

ISO 12800:2017 核燃料技术.氧化铀粉末比表面积的BET测量方法指南

This document gives guidelines on the determination of the specific surface area of as-fabricated uranium dioxide powder by volumetric or gravimetric determination of the amount of nitrogen adsorbed on the powder, and can be applied to other similar materials, e.g. U3O8, UO2-PuO2 powders, and other bodies with similar surface areas, e.g. powder granules or green pellets, provided that the conditions described are fulfilled. Modifications using other adsorbing gases are included. The method is relevant as long as the expected value is in the range between 1 m2/g and 10 m2/g.

Nuclear fuel technology - Guidelines on the measurement of the specific surface area of uranium oxide powders by the BET method

NB/T 25070-2017 核电汽轮机叶片用钢

Steel for nuclear power turbine blades

NB/T 25071-2017 核电厂常规岛及BOP机械设备工程建设阶段腐蚀管理导则

Guidelines for Corrosion Management during Construction Phase of Conventional Island and BOP Mechanical Equipment Engineering of Nuclear Power Plants

NB/T 25076-2017 压水堆核电厂常规岛用全绝缘中压浇注母线技术要求

Technical requirements for fully insulated medium voltage cast busbars for conventional islands in pressurized water reactor nuclear power plants

ISO 21484:2017 核能. 燃料技术. 采用重量分析法测定MOX芯块的氧金属比

Nuclear Energy - Fuel technology - Determination of the O/M ratio in MOX pellets by the gravimetric method