同时指出了松装密度对临界堆料高度的影响。
The effect of apparent density on the critical feed height is given as well.
它在继承了热谱与快谱超临界堆芯设计优点的同时，有效地克服了两者的不足。
This new core design was considered to be the hybrid of the existing thermal SCWR and fast SCWR cores.
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。
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.
然后我们有气体冷却反应堆，那能使用超临界二氧化碳或者氦。
And then we have gas cooled reactors which can use supercritical carbon dioxide or helium.
这主要对于一个临界反应堆的中子平衡，它考虑了所有的这些现象。
And it's essentially a neutron balance for a critical reactor and it does consider all of these phenomena.
我们有些事情要担心,在一个反应堆里,我们称那些为临界的安全功能,那大部分需要维护。
We have certain things that we worry about in a reactor and we call those Critical Safety Functions which need to be in general maintained.
如果是复杂模型，例如一张显示着将进入临界状态的核反应堆的图表，则做出如何防止熔炉的决策会很复杂。
If the model is complex-perhaps a diagram showing a nuclear reactor going critical-the decisions on how to prevent a meltdown will be complex.
这份调查报告同时也建议说，核电站工作人员应当在冷却水中加入硼已防止堆芯重新进入核反应临界状态。
The document also recommends that engineers continue adding boron to cooling water to help prevent the cores from restarting the nuclear reaction, a process known as criticality.
日本在1999年就曾发生过一次4级核事故（又称“东海村核事故”——译注），当时在日本核燃料转换公司（Japan NuclearFuel Conversion）的一个燃料厂内，三名正在为反应堆准备燃料的工人引发了一次链式核反应，使反应堆达到临界状态。
Japan itself had a Level 4 accident in 1999, when three workers preparing fuel for a reactor at a Japan Nuclear Fuel Conversion plant triggered a nuclear chain reaction, called a criticality.
建立临界源方向偏倚和指数变换相结合的耦合抽样方法，用于反应堆孔道的屏蔽计算。
The sampling method by coupling criticality source direction biasing and the exponential transform is established for duct shielding calculation.
本文介绍5MW低功率堆(5mwLPR)首次装料及首次临界试验。
The first criticality experiment of 5mw Low Power Reactor (LPR) is described.
选取加速器驱动次临界快堆(ADSFR)进行燃烧武器级钚研究。
An accelerator driven sub critical fast reactor (ADSFR) was used to study the Pu burning of weapons grade.
在快裂变反应堆的临界问题和超临界系统动力学过程的分析中，几何曲率有重要的应用价值。
The geometric buckling is of great value in application to criticality problem and analysis of dynamic process of supercritical system in fast fission reactor.
给出了临界计算所要求的，得自静态反应堆物理的四因子公式。
The four-factor formula obtained in the static reactor physics is given for critical calculation.
介绍了一个计算反应堆临界质量的公式，用来校验双群理论。
A formula calculating the critical mass in reactor is recommended for checking the two-group theory.
由于临界热流密度(CHF)与反应堆安全密切相关，所以人们从实验和理论上都已经对该现象进行了广泛的研究。
Considering the relationship between the phenomena of critical heat flux (CHF) and the safety of nuclear reactor, the research of CHF on experiment and theory has been carried in detail.
建立临界源方向偏倚和指数变换相结合的藕合抽样方法，用于反应堆孔道的屏蔽计算。
The sampling method by coupling criticality source direction biasing and the exponential transform is established for duct shielding calculation.
本文主要分析压水堆在次临界或低功率下发生的失控提捧事故的瞬态特性。
This prensentation mainly analyzes the transient of uncontrolled RCCAwithdrawal from a subcritical or low power condition for PWR.
3程序是球床式高温气冷堆初始临界计算的有效工具。
Therefore, the TRIPOLI - 4.3 code can accurately calculate the initial criticality of high temperature pebble - bed reactors.
计算结果表明，该装置的堆芯布置满足临界和控制要求，能够满足乏燃料临界实验的需求。
The result indicates that the reactor core arrangement satisfies the critical and control request, and can meet the purpose of spent fuel critical experiments.
MW高温气冷实验堆（HTR-10 ）于2 0 0 0年底在中国建成并实现临界，是一项重大的科研成果。
The 10 MW high temperature gas cooled reactor (HTR 10) reached critical in the end of 2000 in China.
采用计算流体力学软件CFX对超临界水冷堆主容器出口管的温度分布进行数值分析。
The numerical analysis was performed on temperature distribution of the outlet nozzles in main vessel of SCWR(supercritical water reactor) by using computational fluid dynamics software CFX.
临界后，堆芯的原子核反应将进入自持式阶段，为今后机组发电和满功率运行创造条件。
Reaching a critical state, the nuclear reaction of the reactor core will enter into the self-sustaining phase, providing conditions for further electricity generation and full power operation.
该核反应堆模块还包括一个或多个加热器，这些加热器被配置为在启动操作期间和在反应堆芯变成临界状态之前向冷却剂添加热。
The nuclear reactor module further includes one or more heaters configured to add heat to the coolant during a startup operation and prior to the reactor core going critical.
由于超临界水堆(SCWR)在系统简化、降低成本和提高热效率上的优势，SCWR的研究在全球范围内得到广泛关注。
Research activities of supercritical water reactor (SCWR) have been carried out worldwide, aiming at cost reduction by system simplification and higher thermal efficiency.
由于超临界水堆(SCWR)在系统简化、降低成本和提高热效率上的优势，SCWR的研究在全球范围内得到广泛关注。
Research activities of supercritical water reactor (SCWR) have been carried out worldwide, aiming at cost reduction by system simplification and higher thermal efficiency.
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