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核燃料技术 硝酸溶液中毫克量钚的测定 铈(Ⅳ)氧化和铁Ⅱ还原后用重铬酸钾电位滴定法
Nuclear fuel technology - Determination of milligram amounts of plutonium in nitric acid solutions - Potentiometric titration with potassium dichromate after oxidation by CE(IV) and reduction by FE(II)
参考页数:10P.;A4
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二氧化铀粉末和烧结芯块中碳含量的测定 高频感应炉燃烧 滴定法/库仑法/红外吸收法
Determination of carbon content in uranium dioxide powder and sintered pellets - High-frequency induction furnace combustion - Titrimetric/coulometric/infrared absorption methods
参考页数:13P.;A4
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核动力反应堆用燃料组件标识
Identification of fuel assemblies for nuclear power reactors
参考页数:7P.;A4
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核能. UO2, (U,Gd)O2和(U,Pu)O2烧结芯块中氮含量的测定. 惰性气体萃取和电导检测法
Nuclear energy - Determination of nitrogen content in UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets - Inert gas extraction and conductivity detection method
参考页数:5P.;A4
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热室用元件.遥控设计的要求
Components for hot cells - Requirements on design for remote handling
参考页数:29P.;A4
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未受辐照的混合氧化燃料芯块 (U, Pu) O2中钚硝酸溶解度的测定
Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2
参考页数:13P.;A4
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核能. PuO2和UO2粉末以及UO2, (U,Gd)O2和(U,Pu)O2烧结芯块中总氢含量的测定. 惰性气体萃取和电导检测法
Nuclear energy - Determination of total hydrogen content in PuO2 and UO2 powders and UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets - Inert gas extraction and conductivity detection method
参考页数:13P.;A4
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α光谱分析测定含铀核燃料溶液中铀235同位素含量
Determination of the <(hoch)232>U isotopic content in uranium containing nuclear fuel solutions by spectrometry
参考页数:3P.;A4
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热室用元件.第1部分:遥控设计的要求
Components for hot cells - Part 1: Requirements on design for remote handling
参考页数:16P.;A4
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