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reactor safety
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  反应堆安全
     The Principles and movement characteries of the hydraulic dynamic pressure drive for control rods in 5 MW district heating reactor are described with stress on analysis of its effects on reactor safety features.
     介绍了5MW供热堆控制棒流体动压传动的原理及运动特性,并着重分析了它对反应堆安全特性的影响。
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     It shows that if loss of power accident occurs at rated reactor power, the operation of a small auxiliary pump instead of the main pump (at rotation speed of 1500 rpm) can effectively cool the core and assure the reactor safety.
     这表明反应堆额定功率运行时发生断电事故,利用事故泵代替重水泵(1500rpm)进行事故冷却,能够满足要求确保反应堆安全
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     The computing results were given for accident source term described in Reactor Safety Study of USA.
     给出了对具有代表性的美国《反应堆安全研究》的事故源项的计算结果。
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     The PWR in-core temperature detection device,which is one of measures to ensure reactor safety operation,is to monitor and diagnose reactor thermal power output and in-core power distribution.
     压水反应堆堆内温度测量装置是监测反应堆热功率输出及堆内功率分布情况、保证反应堆安全运行的手段之一。
短句来源
     The P\VR in-core temperature detection device, which is one of measures to insure reactor safety operation,is to monitor and diagnose reactor thermal power output and in-core power distribution.
     压水反应堆堆内温度测量装置是监测反应堆热功率输出及堆内功率分布情况、保证反应堆安全运行的手段之一。
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  堆安全
     State of Arts and Outlook of Research Reactor Safety Management Promoted by IAEA
     国际原子能机构(IAEA)研究堆安全管理现状及展望
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     The fast reactor safety analysis is the foundation and key of FBR research work.
     快堆安全分析是快堆研究工作的基础和重点。
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     Many parameters related to reactor safety should be ensured in thermal-hydraulic design for a new type reactor.
     对于一个新型研究堆,在热工水力设计中有很多涉及研究堆安全的参数需要确定。
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     The method can be used in fast reactor safety analysis and simulating calculation of velocity and temperature in heat exchanger of industry.
     对该问题的研究结果可应用于快堆安全分析以及工业换热设备内流场和温场的模拟计算。
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     Through the calculation the meutron spectrum has been given for the normalfast experiment reactor core and mock-up core with 50 percent of normal Nadensity. It would be useful for fast reactor safety analysis.
     计算给出了实验快堆正常芯部和模拟钠密度降低50%时的中子能谱,计算结果有助于快堆安全特性分析。
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  “reactor safety”译为未确定词的双语例句
     Preliminary Analysis of Fusion-Fission Hybrid Reactor Safety
     聚变-裂变混合堆安全性初探
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     These results provide some important reference values for the shielding design of the reactor, which supply the scientific basement to the reactor safety.
     这些结果为反应堆屏蔽设计提供重要的参考价值,为反应堆的安全性提供了科学依据。
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     Promoting Technical Innovation and Insuring Urea Reactor Safety
     力主技术创新 保障尿塔安全
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     Bridge, crane beam, sleeper, ocean structure, pressure institution and nuclear reactor safety shell are often endured stress from many circle times and biggish repetition loading, and fatigue collapse is very easy accrued because of long and repeating loading.
     桥梁、吊车梁、轨枕、海洋结构、压力机构和核反应堆安全壳等经常承受循环次数较多而重复荷载较大的结构,在长期的反复荷载的作用下极容易发生疲劳破坏。
短句来源
     The results verify that the core is in no danger of becoming uncovered before an operator response in 10 min, which verifies the reactor safety.
     对堆芯水位的计算结果表明:操作员在10min内对事故进行干预情况下堆芯不裸露,反应堆是安全的。
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  reactor safety
Of greater importance to reactor safety is the reactivity of tungsten with steam.
      
Over the years, we have developed several experimental facilities to provide data for fusion reactor safety analyses.
      
Approach for fusion reactor safety and fusion safety work in Russia
      
Quite possibly the main constraint on expanded use of fission will be neither lack of fuel nor high costs, but perceived environmental liabilities-radioactive wastes, reactor safety, and links to nuclear weaponry.
      
Radiological aspects of fusion reactor safety: Risk constraints in severe accidents
      
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This paper presents the results on cooling mode investigation during loss of power accident of the heavy water research reactor. Theoretical analysis are in satisfactory agreement with experimental measurement results. It shows that if loss of power accident occurs at rated reactor power, the operation of a small auxiliary pump instead of the main pump (at rotation speed of 1500 rpm) can effectively cool the core and assure the reactor safety.

本文总结了研究性重水反应堆断电事故冷却方式研究结果。理论计算和实验测量的各种结果比较,二者符合较好。这表明反应堆额定功率运行时发生断电事故,利用事故泵代替重水泵(1500rpm)进行事故冷却,能够满足要求确保反应堆安全。

In this paper,the newer data have been used for making the multi-groupaccurate treatment of elastic scattering in light and medium elements in fastreactors.In which the resonance treatment is more careful.Total 491 resonancepeaks including Na,Fe,Cr and Ni elements are calculated and the contributionfrom P wave is also considered.Through the calculation the meutron spectrum has been given for the normalfast experiment reactor core and mock-up core with 50 percent of normal Nadensity.It would be useful for fast...

In this paper,the newer data have been used for making the multi-groupaccurate treatment of elastic scattering in light and medium elements in fastreactors.In which the resonance treatment is more careful.Total 491 resonancepeaks including Na,Fe,Cr and Ni elements are calculated and the contributionfrom P wave is also considered.Through the calculation the meutron spectrum has been given for the normalfast experiment reactor core and mock-up core with 50 percent of normal Nadensity.It would be useful for fast reactor safety analysis.

本文用较新的数据,对快堆中存在的轻元素和中等质量元素的弹性散射作了多群精确处理。其中共振计算比较细致,共计算了 Na、Fe、Cr、Ni 等元素共振峰491个,并考虑了 p 波的贡献。计算给出了实验快堆正常芯部和模拟钠密度降低50%时的中子能谱,计算结果有助于快堆安全特性分析。

In spite of nuclear reactor safety has effects of importance to overal nuclear ship safety, ultimate safety of the reactor and the crew and the environment lies with the safety of the ship itself. Therefore, it is shouln't that the principle of"The Reactor Safety Come First" is used to determine correletion between the reactor safety and the ship safety as land-based nuclear power plants.

尽管核反应堆的安全对船的总体安全具有重大影响,但是反应堆,船员以及环境的安全最终依赖于船体的安全。因此,不应当象陆基电站一样使用“反应堆安全第一”的准则处理反应堆安全与船体安全之间的关系。

 
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