NF M60-406-2009

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

DIN 25463-1-1990

轻水原子反应堆核燃料的衰变功率计算不可回收的核燃料

Decay heat power in nuclear fuels of light water reactors; non-recycled nuclear fuels

适用范围：The decay heat power of nuclear fuels is the thermal power produced by radioactive decay of the fission products and activation products of the nuclear fuel following shutdown of a nuclear reactor. Thi...

ISO 21483-2013

未照射的混合氧化燃料芯块中钚的销酸含量的测定

Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2

适用范围：ISO 21483:2013 specifies an analytical method for determining the solubility in nitric acid of plutonium in pellets of unirradiated mixed oxide fuel (light-water reactor fuels). The results provide inf...

发布日期：2013-11-01  实施日期：2013-11-01

NF C56-282-3-200-2012

Fuel cell technologies - Part 3-200 : stationary fuel cell power systems -Performance test methods.

ISO 12795-2004

核燃料技术 二氧化铀粉和丸 用杂质修正重力法测定铀和氧化铀比例

Nuclear fuel technology -- Uranium dioxide powder and pellets -- Determination of uranium and oxygen/uranium ratio by gravimetric method with impurity correction

适用范围：ISO 12795:2004 specifies a method of determining the mass fraction of uranium and the oxygen-to-uranium atomic ratio in hyperstoichiometric uranium dioxide (UO2+X) powders and pellets. ISO 12795:2004 i...

发布日期：2004-08-01  实施日期：2004-08-01

EJ/T 679-2005

脉冲堆铀-氢化锆燃料元件

Specification for uranium-zirconium hydrogenate fuel element of pulsed reactor

适用范围： 本标准规定了脉冲堆铀-氢化锆燃料元件(下称燃料元件)及其材料、零件的技术要求、取样与试验方法，供方应提交的燃料元件质量文件以及燃料元件包装、运输、贮存要求。　　本标准适用于燃料元件及其材料、零件的设计、采购、制造...

实施日期：2005-07-01

NF M60-430-2-2008

Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 2 : data standardization for tank calibration.

NF M60-455-2007

Nuclear energy - Nuclear fuel technology - Scaling factor method to determine the radioactivity of low- and intermediate-level radioactive waste packages generated at nuclear power plants.

EN 62282-3-1-2007

Fuel cell technologies - Part 3-1: Stationary fuel cell power systems - Safety

DIN 25422-1994

放射性材料的保存;对保存装置及放置房间的防辐射、防火及防盗方面的要求

Storage of radioactive materials - Requirements on protection against radiation, fire and theft to be met by storage facilities

适用范围：This document consists of safety related requirements for the planning and installing of storage facilities against radiation, fire and theft. The requirements correspond with #21; 6 und #21; 74 radiat...

实施日期：1994-08-01

ISO 10981-2004

核燃料技术 后处理厂溶解器溶液中铀的测定 液相色谱法

Nuclear fuel technology -- Determination of uranium in reprocessing-plant dissolver solution -- Liquid chromatography method

适用范围：ISO 10981:2004 specifies an analytical method for determining the uranium concentration between 0,1 g/l and 400 g/l in nitric acid solutions of irradiated fuel from light-water reactors, gas-cooled rea...

发布日期：2004-06-01  实施日期：2004-06-01

EJ/T 745-1992

轻水堆核燃料衰变热功率的计算

实施日期：1993-06-01

NB/T 25012-2013

核电厂汽水分离再热器系统调试导则

Commissioning guidelines for moisture separator reheater system of nuclear power plant

适用范围：本标准规定了压水堆核电厂汽水分离再热器系统的调试内容、试验要求。 本标准适用于压水堆核电厂汽水分离再热器系统调试。

发布日期：2013-06-08  实施日期：2013-10-01

NF M60-461-2006

Nuclear energy - Determination of Gd2O3 content in gadolinium fuel blends and gadolinium fuel pellets by atomic emission spectrometry using an inductively coupled plasma source (ICP-AES).

DIN 25401-7-2002

核技术概念.第7部分:核反应堆安全

Terms and definitions of nuclear technology - Part 7: Safety of nuclear installations

ISO 18213-3-2009

核燃料技术 用于核材料衡算计量的容器校准和容量测定 第3部分:统计方法

Nuclear fuel technology -- Tank calibration and volume determination for nuclear materials accountancy -- Part 3: Statistical methods

适用范围：ISO 18213-3:2009 presents statistical procedures that can be applied to tank calibration and volume measurement data for nuclear materials accountancy tanks. In particular, ISO 18213-3:2009 presents se...

发布日期：2009-03-01  实施日期：2009-03-01

ASTM C1297-2003

核燃料循环材料分析的实验室分析人员资格指南

Standard Guide for Qualification of Laboratory Analysts for the Analysis of Nuclear Fuel Cycle Materials

适用范围：<p id="s00009">This is one of a series of guides designed to provide guidance for implementing activities that meet the requirements of a sound laboratory quality assurance program. The first of these,...

实施日期：2003-07-10

DIN 25401-8-2002

核技术概念.第8部分:辐射防护

Terms and definitions of nuclear technology - Part 8: Radiation

EN 62282-5-1-2007

Fuel cell technologies - Part 5-1: Portable fuel cell power systems - Safety

GB/T 15146.11-2004

反应堆外易裂变材料的核临界安全 基于限制和控制慢化剂的核临界安全

Nuclear criticality safety for fissile materials outside reactor--Nuclear criticalitysafety based on limiting and controlling moderators

适用范围：本部分规定了通过在慢化剂控制区中限制和控制慢化剂保证易裂变材料核临界安全的方法和要求。　　本部分适用于慢化剂控制区中通过限制和控制慢化剂来实现易裂变材料操作的核临界安全。

发布日期：2004-05-27  实施日期：2004-12-01