辐照燃料

辐照燃料元件冷却系统生物医学辐照用反应堆

Spent fuel cooling system biomedical irradiation reactor

辐照燃料元件冷却系统

Spent fuel cooling system

通过实验测得反应堆停堆时刻裂变产物~（137）CS、~（148）Nd等监测体的浓度值，进而推算出辐照燃料元件的燃耗值是通常采用的方法。

Usually , concentration of fission product monitors ~ ( 137 ) Cs and ~ ( 148 ) Nd are measured experimentally , from which burnup of irradiation fuel element can be derived .

未辐照燃料棒内氢来源的研究

A study on internal sources of hydrogen in unirradiated fuel rod

核动力堆辐照燃料燃耗的辐照史校正方法

Irradiation history correction method of burnup of the nuclear power reactor

辐照核燃料运输容器的撞击分析

Analysis of Impact Response of Nuclear Fuel Shipping Containers

铀氢化锆元件小型动力堆应用可行性分析辐照二氧化铀燃料元件氢化锆慢化反应堆系统

Feasibility Analysis for Application of Compact Power Reactor Fuelled with Uranium Zirconium Hydride

辐照核燃料后处理厂辐照铀后处理控制装置

Used fuel reprocessing plant irradiated uranium reprocessing control assembly

辐照核燃料后处理厂

Used fuel reprocessing plant full sewage treatment plant

海上安全运输辐照核燃料和其他核材料工作组

Working Group on the Safe Carriage of Irradiated Nuclear Fuel and other Nuclear Material by Sea

辐照二氧化铀燃料元件

Irradiated uranium dioxide fuel element

冷却辐照的燃料组元

Cooling irradiated fuel element

根据核能发展规划，至2000年从我国核电站卸出的辐照核燃料估计达1900吨左右。

According to the nuclear program the spent fuel discharged from Chinese nuclear power stations by 2000 is estimated at about 1900t .

辐照后核燃料中镅的放化分析

Radiochemical analysis of am in irradiated fuel

锆锡合金的辐照生长及在燃料组件结构设计中的考虑

Irradiation-Induced Growth of Zircaloy and Its Effect on the Mechanical Design of Fuel Assemblies

关于辐照过的核燃料的海运问题原子能机构/海事组织联合小组

Joint IAEA / IMO Group on the Carriage of Irradiated Nuclear Fuel by Sea

核动力堆辐照后的核燃料元件中铀和钚的测定方法

A Review of the Metnods for the Determination of the Uranium and Plutonium in the Post-irradiated Nuclear Fuel Elements of Power Reactor

本文概述了核动力堆辐照后的核燃料元件分析样品的特点、样品的溶解和样品中铀和钚的测定方法。

In this review the characteristics and dissolutions of the Samples and the methods for the determination of the uranium and plutonium in the post-irradiated nuclear fuel elements of power reactors are presented .