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为测定选定同位素以及评估燃料燃耗的废核燃料分析的标准实施规程

Standard Practice for Analysis of Spent Nuclear Fuel to Determine Selected Isotopes and Estimate Fuel Burnup

铀和钚燃料中原子裂变百分比的标准试验方法(钕-148法)

Standard Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method)

用高分辨率γ射线光谱分析法对照射过的核燃料中的铯137的标准试验方法

Standard Test Method for Determining the Content of Cesium-137 in Irradiated Nuclear Fuels by High-Resolution Gamma-Ray Spectral Analysis

轻水反应堆核燃料衰变热功率的计算.第1部分:压水反应堆的氧化铀核燃料

Calculation of the decay power in nuclear fuels of light water reactors - Part 1: Uranium oxide nuclear fuel for pressurized water reactors

轻水反应堆核燃料衰变功率的计算第1部分：压水反应堆用氧化铀核燃料

Calculation of the decay power in nuclear fuels of light water reactors - Part 1: Uranium oxide nuclear fuel for pressurized water reactors

带轻水反应堆的核电站燃料槽中核燃料元件在搬运和储存时燃耗应考虑的临界安全性

Criticality safety taking into account the burnup of fuel elements when handling and storing of nuclear fuel elements in fuel pools of nuclear power stations with lightwater reactors

在轻水反应堆核电站燃料池中处理和储存核燃料元件时考虑燃料元件燃耗的临界安全

Criticality safety taking into account the burnup of fuel elements when handling and storing nuclear fuel elements in fuel pools of nuclear power plants with lightwater reactors

在轻水反应堆核电站燃料池中处理和储存核燃料元件时考虑燃料元件燃耗的临界安全

Criticality safety taking into account the burnup of fuel elements when handling and storing nuclear fuel elements in fuel pools of nuclear power plants with lightwater reactors

考虑容器中受辐射轻水反应堆燃料组件运输和储存的燃料燃耗的临界安全

Criticality safety taking into account the burnup of fuel for transport and storage of irradiated light water reactor fuel assemblies in casks

考虑容器中受辐射轻水反应堆燃料组件运输和储存的燃料燃耗的临界安全

Criticality safety taking into account the burnup of fuel for transport and storage of irradiated light water reactor fuel assemblies in casks

核临界安全.包含PWR UOX燃料的系统评估.临界燃耗效益方法

Nuclear criticality safety - Evaluation of systems containing PWR UOX fuels - Bounding burnup credit approach