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临界堆
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  critical reactor
     The results show that reactor driven by accelerator do not happen prompt critical easily, its safety characteristics are better than critical reactor's, the higer the subcritical degree is , the better the safety is.
     结果表明 :驱动堆不易发生瞬发临界 ,其安全特性优于临界堆 ,次临界度越深 ,安全性越好 ;
短句来源
     The control loop of reactor driven by accelerator has a little time constant, a little overshoot, and short regulating time, its control characteristics also are better than critical reactor's.
     驱动堆控制回路具有小的时间常数和超调量 ,调整时间短 ,控制特性亦优于临界堆
短句来源
     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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  相似匹配句对
     THE MEASUREMENTS OF CRITICAL MASS WITH URANIUM FUELS ELEMENTS AND THORIUM RODS
     钍——鈾栅零功率临界实验
短句来源
     Trie Heap
     Trie
短句来源
     (M, H)-Critical Matrices
     (M,H)-临界矩阵
短句来源
     Initial criticality calculation for the high temperature reactor in the ASTRA critical facility
     高温临界实验装置ASTRA的初始临界计算
短句来源
     A Way of Calculating the Volume of a Sand Heap
     沙问题
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  critical reactor
Can only a part of a critical nuclear reactor form a critical reactor
      
Accelerator-driven sub-critical reactor system (ADS) for nuclear energy generation
      
A noniterative method for solving the adjoint equations of a critical reactor
      
Spatial fluctuations of neutron and power distribution in critical reactor
      
The possible range of variation of the reactivity of a subcritical and a critical reactor with one control rod extracted is analyzed for the actual states of the power-generating units of a nuclear power plant with RBMK reactors.
      
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We present the principle and progress of accelerator driven sub critical reactors as the new generation of clean nuclear energy systems. Some suggestions on further work are given.

介绍了新一代干净的核能———加速器驱动的次临界堆的原理和国际研究进展,并对国内如何开展这方面的研究提出了建议

The importance of partitioning transmutation of nuclear wastes and the advanced nuclear energy systems (ANES) are emphasized. The physical bases of transmutation of nuclear wastes and of three kinds of ANES are elucidated. The chemical separation requirements and their present status are reviewed briefly.The certain feature of three kinds of ANES are also discussed. Finally, an overall strategic plan for exploring such ANES in China is suggested.

阐述了核废物分离-嬗变(P-T)处置和先进核能系统(ANES)的重要性及其物理基础,讨论了对化学分离的要求和现状,并对裂变堆、聚变-裂变混合堆、加速器驱动次临界堆等核废物嬗变炉为主的3类先进核能系统作了简要讨论。最后,对我国开展先进核能系统研究的发展战略提出了建议。

This work analyses the main properties of reactor core physics for accelerator driven sub critical reactor. These properties include the breeding of fission nuclides, the condition of equilibrium, the accumulation of long lived radioactive wastes, the affect from poison of fission products, as well as the thermal power output and the energy gain for sub critical reactor. The comparisons between thermal and fast system for main properties are carried out. The properties for a thermal fast coupled system...

This work analyses the main properties of reactor core physics for accelerator driven sub critical reactor. These properties include the breeding of fission nuclides, the condition of equilibrium, the accumulation of long lived radioactive wastes, the affect from poison of fission products, as well as the thermal power output and the energy gain for sub critical reactor. The comparisons between thermal and fast system for main properties are carried out. The properties for a thermal fast coupled system are also analysed in present work.

分析了加速器驱动次临界堆堆芯的裂变核素增殖和平衡条件、主要长寿命放射性废物的积累、裂变产物毒性的影响及次临界堆的运行周期、输出功率和能量增益等主要性质,并对次临界热堆和次临界快堆的物理性质进行了比较。在简单的球形几何条件下,分析了铀-铅和钍-重水组成的快-热耦合的次临界系统的物理性质。

 
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