nuclear temperature的例句大全

The self-consistent field equations at finite nuclear temperature& the generalized HFB equations

温度不为零的自洽场方程&HFB方程的推广

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The particle multiplicity is also given which depends on nuclear temperature and nuclear friction constant.

文中还描述了粒子多重数的计算,并讨论了与核温和与粘滞系数的关系.

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In order to study the variation of shell effects as well as pairing effects with nuclear temperature, we have extended the work of Sano and Yamasaki to generalize the HFB equations to finite nuclear temperature with the help of variational principle.

为了研究壳效应以及对效应随核温度的变化，我们借助于变分原理扩展了Sano和Yamasaki的工作，把HFB方程推广到核温度不为零的情况。

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Liquid gas Phase Transition of Highly Excited Nuclear Matter and Nuclear Temperature

高激发核物质液-气相变与核温度

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The friction behavior of three kinds of graphite used for nuclear reactors was tested by SRV standard high temperature friction tester under the helium and air environments The friction coefficients for the three kinds of graphite all increase with the friction speed increases.

在高温摩擦实验机SRV上对三种反应堆用石墨的摩擦系数进行了测试，实验条件分别是高温气冷堆冷却剂氦气环境和空气环境。

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In order to recycle Tokamak exhaust gases expelled from nuclear fusion reactors, the hydrogen isotope mixture gas which contain the impurities of oxygen and nitrogen has been purified by the means of the method of catalytic deoxygenization and cryogenic ( i.e. liquid nitrogen temperature 77.4 K) absorption.

为了回收利用核聚变反应堆排出的托卡马克废气，将含有氧、氮杂质的氢同位素混合气，通过催化剂脱氧，低温（774K）吸附的方法，进行了净化处理。

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The delayed supercritical process of nuclear reactor with temperature feedback and initial power while inserting small step reactivity(ρ_0 < β) is investigated.

对输入小阶跃反应性（ρ0

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The modeling problem of PWR nuclear power station core is expound, critical reactor neutron dynamics model, temperature effect neutron dynamics model and core transfer of heat model is built up apply to microcomputer artificial nuclear power station.

阐述了PWR核电站堆芯的模型化问题，建立了适用于微机仿真的核电站的临界堆中子动力学模型、温度效应中子动力学模型和堆芯热传递模型。

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The Study on the High Temperature Property of Small-Type Photomultiplier Used in Nuclear Detection Well

核测井用小型光电倍增管高温特性的研究

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The negative absolute temperature system of the nuclear spin is discussed statistically. And the expressions of S and CB of typically nuclear spin negative tempera-ture system are introduced and analysed.

本文对负绝对温度系统进行了统计讨论，导出并分析了典型的核自旋负温系统的S和C＿B的表达式。

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Laser cladding of Co base alloy on the nuclear valve sealing surface are performed with a 5 kW CO 2 transverse flowing laser. The microstructure and the high temperature impact slide wear resistance of the laser cladded coating and the plasma cladded coating are studied.

应用5kW横流CO2激光器对核阀阀瓣密封面进行Co基合金的激光熔覆处理，对激光熔覆层和等离子熔涂涂层进行了显微组织分析和抗高温冲击滑动磨损性能对比试验研究。

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Study on Contents of Nuclear Acid, Protein and Chlorophyll in Hypocotyl of Tomato Seed with Different Temperature Treatment

不同温度处理番茄种子后胚轴内含物含量的变化

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Study on Microstructure and High Temperature Wear Resistance of Laser Cladded Nuclear Valve Clack

核阀阀瓣激光熔覆层显微组织和耐高温磨损性能研究

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Simulation Study of Internal Model Control System of Refrigerant Average Temperature of Nuclear Reactor

核电站反应堆冷却剂平均温度内模控制系统仿真

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The optional techniques of nuclear hydrogen production, including steam methane reforming ( SMR), high temperature electrolysis ( THE) and thermochemical cycle, was introduced and reviewed.

本文对核能制氢的工艺，包括甲烷蒸气重整、高温电解和热化学循环进行了综述；

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High-performance sphere valve, which can resists high temperature, high pressure, wearing, thermal impact and heat erosion, is one of key components used in coal liquefaction engineering, steel smelting, petroleum chemical engineering and nuclear power.

在煤液化工程、钢铁冶炼、石油化工、核电等重大工程项目中，耐高温、耐高压、耐磨损、抗热冲击、抗热腐蚀球阀一直是关键部件之一。

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Control Rod Drive Line Test in High Temperature Still Water for Qin Shan Nuclear Power Plant

秦山核电厂控制棒驱动线热态静水试验

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Analysis for Ling' ao Nuclear Power Station unit 1 exciter No.11 bearing white metal damage and its operating temperature abnormal high

岭澳核电站1号机组励磁机11号轴瓦乌金损坏及运行温度高的原因分析

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Graphical modeling for simulation of average temperature control systems for nuclear units' reactors

核电机组反应堆平均温度控制仿真系统图形化建模中温平板型SOFC电堆的模拟与控制

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Zirconium alloy was chosen for use in the core of water-cooled nuclear reactors because of its low thermal neutron capture cross-section, reasonable mechanical properties and adequate corrosion resistance in high temperature water.

锆合金因为具有良好的抗高温水及过热蒸汽的腐蚀性能、良好的力学强度和塑性以及较低的热中子吸收截面，在反应堆内得以广泛应用。

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