机译:超高温反应堆核氢炼钢的优异性能评估
Nuclear Hydrogen and Heat Application Research Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi,Higashiibaraki-gun, Ibaraki-ken, 311-1393 Japan;
Nuclear Hydrogen and Heat Application Research Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi,Higashiibaraki-gun, Ibaraki-ken, 311-1393 Japan;
Nuclear Hydrogen and Heat Application Research Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi,Higashiibaraki-gun, Ibaraki-ken, 311-1393 Japan;
nuclear hydrogen steelmaking; hydrogen reduction; CO_2 emissions; very high temperature reactor; nuclear hydrogen production; is process;
机译:超高温反应堆核氢炼钢的优缺点评估
机译:使用超高温反应堆的核氢炼钢厂的工艺流程图评估,可实现高效的钢铁生产,并减少CO_2排放
机译:VHTR-IS(超高温反应器和碘硫法)核氢炼钢工艺流程图模型评估
机译:用核反应堆能力匹配氢气生产需求:先进的高温反应器
机译:模块化氦反应堆的设计修改,可进行更高温度的运行以及核氢生产工艺的可靠性研究。
机译:高温氦加热碘化碘化物分解反应器中熵产生率的最小化
机译:高温反应器的核氢炼钢的优点评估