1) MOX fuel pellet
MOX燃料芯块
1.
Based on the comparability of the thermodynamics and phase diagrams of U-Ce-O system and U-Pu-O system, and the analysis of the manufacturing simulation technology of MOX fuel pellets, it is possible that the U-Ce-O system is used to simulate the U-Pu-O system in the manufacturing test of MOX fuel pellets.
Pu元素的放射性和毒性给MOX燃料芯块制造技术带来很大不便。
2) MOX fuel
MOX燃料
1.
Development progress of the CEFR-MOX fuel;
中国实验快堆MOX燃料研究进展
2.
On the basis of the introduced experimental information,the process of calcu- lating the effective multiplication factor of MOX fuel experimental reactors using MCNP is introduced.
简单说明计算所用的实验资料,在此基础上,介绍了采用MCNP计算MOX燃料实验堆有效增殖系数的过程。
3.
The time-average and instantaneous calculations of CANFLEX bundle with MOX fuel in a CANDU reactor are performed, and computational results demonstrate that the maximum bundle power and channel power are under the permissible limits.
针对CANFLEX组件装载MOX燃料在CANDU重水堆中的应用进行了时均和瞬态验证计算。
3) MOX nuclear fuel
MOX核燃料
1.
The purpose of our work is to find a way for application of depleted uranium inCANDU reactor by using MOX nuclear fuel of depleted U and Pu instead of naturaIuranium.
对以贫铀和钚组成MOX核燃料替代CANDU堆中的天然铀的可能性进行了探讨，从而开辟贫铀用于核能的途径。
5) pellet fuel
芯块燃料
6) simulative MOX fuel
模拟MOX燃料
1.
A quantitative method for determination of U and Ce in simulative MOX fuel samples by binary intensity ratio and X-ray fluorescence spectrometry is studied.
建立了二元比例 X射线荧光光谱法定量测定模拟MOX燃料中U和Ce含量的方法。
补充资料：燃料芯块
分子式：
CAS号：
性质：为核燃料元件的核心部分，即由易裂变材料235U和239Pu构成。核燃料可分为金属型、陶瓷型和弥散型，外面敷以铝合金、镁合金、锆合金以及不锈钢等包壳材料。燃料芯块的表面必须机械磨光，以保证与包壳材料的配合。为适应燃料芯块的辐照肿胀，芯块的上下面压制成凹碟形。要选择与燃料芯块相容性好的包壳材料。
CAS号：
性质：为核燃料元件的核心部分，即由易裂变材料235U和239Pu构成。核燃料可分为金属型、陶瓷型和弥散型，外面敷以铝合金、镁合金、锆合金以及不锈钢等包壳材料。燃料芯块的表面必须机械磨光，以保证与包壳材料的配合。为适应燃料芯块的辐照肿胀，芯块的上下面压制成凹碟形。要选择与燃料芯块相容性好的包壳材料。
说明：补充资料仅用于学习参考，请勿用于其它任何用途。
参考词条