堆芯中的高温让一些操作员认为堆芯已完全暴露；其他一些人并不相信温度的读数。
High temperatures in the core lead some to believe that the core is uncovered; others do not trust the temperature readings.
（反应堆）使用的燃料具有强放射性并且在高温下自发燃烧。
The used fuel is extremely radioactive and ignites spontaneously at high temperatures.
你们可以观察高温气体反应堆，但是，这差不多是陈旧的信息，因为我们要讲的是一个不同的技术，那比我们在这提议的要陈旧。
You can look at the high temperature gas reactor but this is more or less dated information because we're going to a different technology than what is being proposed here.
另一种高温的气体反应堆是，我们称之为卵石层反应堆。
Another type of high temperature gas reactor is what we call a pebble bed reactor.
现在，卵石层反应堆有相同的基本，安全特征和高温棱柱反应堆一样，因为它有一个熔化的核心。
Now the pebble bed reactor has the same basic safety features as a high temperature prismatic reactor in a sense that it has a meltdown free core.
当反应堆的核心铀和锆合金的燃料棒融化时，它需要2,200摄氏度的高温，同时释放大量辐射微粒。
This is when the uranium and the zircalloy fuel rods at the heart of the reactor melt. It occurs at temperatures above 2, 200c, releasing highly radioactive particles.
当反应堆的核心铀和锆合金的燃料棒融化时，它需要2,200摄氏度的高温，同时释放大量辐射微粒。
This is when the uranium and the zircalloy fuel rods at the heart of the reactor melt. It occurs at temperatures above 2,200c, releasing highly radioactive particles.
接下来的问题是，反应堆的高温和谐是否已经在容器内融化了，并且释放了放射性物质。
The next question is whether the hot cores will actually melt through the containers, spreading the radioactive materials, shooting them into the ground.
这将有助于研究人员挑选出最适合热核反应堆的建筑材料，因为热核反应堆与高温等离子体会发生接触。
It will help to choose optimal construction materials for elements of the thermonuclear reactor that contacts with hot plasma.
此举是增加水量来吸收热量，并要确保反应堆完全被水覆盖，这样高温就不会进一步损坏反应堆。
This greatly increased the amount of water available to soak up the heat, and should have made sure that the reactor was fully covered by water and thus not hot enough to damage itself any further.
气体透平氦气模块堆（GT-MHR）标准题是国际原子能机构（IAEA）关于“高温气冷堆在事故工况下的热传输和余热载出”问题的合作研究计划（CRP）的一部分。
The benchmark problem for GT-MHR plutonium burner accidents is a part of the IAEA Coordinated Research Program(CRP) on "heat transport and afterheat removal for GCR under accident conditions".
反应堆压力容器作为反应堆的基本安全屏障，承受高温、高压且内部包含具有放射性的工作介质。
As the basic safe wall of nuclear reactor, the reactor pressure vessel not only bears high temperature and high pressure, but also contains radioactive working substance.
概述了将在我国建造的10兆瓦模块式高温气冷实验堆的设计特性、安全概念及安全分析。
The general design features of 10 MW HTR Test Module, which will be built in China, and its basic safety concept and analysis are summarized.
非能动余热排出系统是模块式高温气冷堆(MHTR)实现固有安全性的重要保证。
Passive residual heat removal system is the key assurance for the inherent safety of modular high-temperature gas-cooled reactor (MHTR).
概述了作为钠冷快堆结构材料和包壳材料的国产奥氏体不锈钢以及作为蒸汽发生器管材的铁素体低合金钢与高温钠相容性研究的主要结果和现状。
Main results and situation of the compatibility investigation for austenic stainless steels and ferritic low alloy steels with high temperature sodium are summarized in this paper.
本文还将这些特点和高温气冷堆一回路氦气风机的技术要求作了比较。
A comparison is made between the characteristics and technical requirement of helium circulators used in the primary circuit of high-temperature gas cooled reactors.
介绍了10MW高温气冷实验堆的数字化物理启动中子注量率监测系统的设计和功能。
This paper introduces a design of digital neutron flux monitoring system for 10mw high temperature gas cooled reactor and its performances.
高温气冷堆气轮机循环被认为是将来核能发电领域中最有潜力的方案之一。
The high temperature gas cooled reactor (HTGR) coupled with the gas turbine cycle is considered as one of the leading candidate concepts for future nuclear power deployment.
MW高温气冷实验堆(HTR -10)的仪表与控制系统采用了先进的数字化分布式计算机控制系统(DCS)。
Advanced digital distributed computer system (termed DCS) is adopted in 10mw High Temperature Gas cooled test Reactor (termed HTR 10).
讨论了10MW高温气冷实验堆(HTR 10)气体透平总体方案设计中应考虑的主要因素。
The article discusses the key issues which factor into the conceptualization of the gas turbine cycle to be coupled to the 10mw high temperature gas cooled test reactor (HTR 10).
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.
为了制备高温气冷反应堆用燃料芯核，致密uo_2微球，研究了一种新的溶胶-凝胶工艺。
A new kind of sol - gel process for preparation of dense UO2 kernels used for HTGR (High Temperature Gas cooled Reactor) has been developed in our institute.
石墨广泛地用做核反应堆慢化材料、反射层材料和堆芯结构材料，在高温气冷堆中还用来做燃料元件。
In nuclear reactors, graphite is used widely as moderators, reflectors, constructive materials of reactor core and fuel elements in high temperature gas cooled reactors.
在10MW高温气冷堆(HTR - 10)中，由于石墨构件的磨损会产生石墨粉尘，将影响反应堆的正常运行。
In 10mw High Temperature Gas-cooled reactor (HTR-10), the wear of graphite components generates the graphite dust to influence the normal working of the reactor.
讨论了高温气冷堆元件球后处理首端过程用固定床燃烧法去除石墨的可行性。
The feasibility of removing graphite by fixed bed burning technology in the headend process of HTGR graphite ball-element reprocessing is discussed.
高温气冷堆乏燃料元件的放射性裂变产物绝大部分滞留在燃料元件中。
The majority radioactive fission products of the spent fuel elements in high temperature gas-cooled reactor(HTGR) is contained in the fuel element.
介绍了10MW高温气冷实验堆反应堆压力容器热电偶贯穿件。
The paper presents the thermocouple penetration assemblies of 10mw high temperature gas cooled reactor (HTR - 10).
高温气冷堆对燃料微球各包覆层的厚度有严格的要求。
The thickness of coatings for the HTGR (high temperature gas cooled reactor) coated fuel particles must meet design requirements.
包覆燃料颗粒是高温气冷堆燃料元件的关键组成部分。
The coated fuel particle is the key fuel element in the high temperature gas cooled reactor (HTGR).
包覆燃料颗粒是高温气冷堆燃料元件的关键组成部分。
The coated fuel particle is the key fuel element in the high temperature gas cooled reactor (HTGR).
应用推荐