The neutrons are created in a fission reactor, and slowed to incredibly low speeds by materials known as moderators.
这些中子从核反应堆中产生，在减速剂的作用下减到难以置信的低速。
The geometric buckling is of great value in application to criticality problem and analysis of dynamic process of supercritical system in fast fission reactor.
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 principle and structure of high frequency piezoelectric sensor for safe observation of fast fission reactor are introduced, and the testing results are presented.
本文介绍了用于快速中子反应堆安全监测的压电式高频传感器的原理、结构与试验结果。
Blowers move helium gas through the reactor and over the pebbles, where nuclear fission releases large amounts of energy, heating up the helium.
鼓风机将氦气吹过反应堆，经过核裂变释放出大量能量的小球，加热了氦。
Uranium 235 — the fuel inside a nuclear reactor — undergoes nuclear fission.
铀235——反应堆中的燃料——经过核裂变。
But roughly 5 percent of reactor waste is highly radioactive fission products, including plutonium and other actinides.
但是约有百分之五的反应堆废料是高放射性裂变产物，包括钚和其他锕系元素。
The idea behind the reactor was to use the heat generated by fission to heat hydrogen, which would expand, generating the force to push the rocket.
这一试验的原理是运用核裂变产生的热量给氢气加温，导致其膨胀，并产生推动火箭的力量。
Plutonium is produced during nuclear fission, so is present in all reactor cores - the longer the fuel has been there, the more plutonium will be present, up to about 1%.
钚是在核裂变过程中产生的，所以在所有的反应堆中都存在---燃料在反应堆内烧的时间越长，产生的钚就越多，最高可以到1%。
Fast-moving neutrons are produced by fission reaction in a nuclear reactor. Water is commonly used to moderate and control the speed of neutrons.
核电站的核反应堆中，核裂变会产生高速移动的中子，通常是用水去阻隔及控制中子的移动速度。
Fission gas release measurement of reactor fuel rods is one of the main issues of post-irradiation examination, which plays a key role to the evaluation of fuel performance.
反应堆燃料元件的裂变气体释放率测量是辐照后检验的一项重要内容，它对于评价燃料元件的性能起着重要作用。
The majority radioactive fission products of the spent fuel elements in high temperature gas-cooled reactor(HTGR) is contained in the fuel element.
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。
A computer code FDKR and its associated data library AF-DCDLIB have been developed for fusion-fission hybrid reactor radioactivity calculations.
研制了聚变一裂变混合堆放射性计算程序fdkr和配套的衰变链数据库af—DCDL—IB。
This paper presents the thermal analyses for steady state, depressurization and total loss of flow in the tokamak heliumcooling slab fuel element fusion-fission hybrid reactor.
本文对以托卡马克为聚变装置、氦气冷却板状元件包层的聚变-裂变混合堆进行了稳态、卸压和全厂断电断流的热工分析。
This paper presents the thermal analyses for steady state, depressurization and total loss of flow in the tokamak heliumcooling slab fuel element fusion-fission hybrid reactor.
本文对以托卡马克为聚变装置、氦气冷却板状元件包层的聚变-裂变混合堆进行了稳态、卸压和全厂断电断流的热工分析。
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