Results 101 to 110 of about 22,368 (209)
EnergiesThe development of advanced energy materials is critical for the safety and efficiency of next-generation nuclear energy systems. Aluminum alloys present a compelling option due to their excellent neutronic properties, notably a low thermal neutron ...
Przemysław Snopiński +3 more
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Effect of 0.25 and 2.0 MeV He-ion irradiation on short-range ordering in model (EFDA) Fe-Cr alloys
, 2018 The effect of He+ ion irradiation on a distribution of Cr atoms in model (EFDA) Fe(100-x)Cr(x) (x=5.8, 10.75, 15.15) was studied by means of conversion electrons Mossbauer spectroscopy.
Dubiel, S. M. +2 more
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High-dose neutron irradiation of beryllium and titanium beryllide: Summary and outlook
Nuclear Materials and EnergyThe irradiation experiment conducted in the HFR material testing reactor, under conditions simulating the operating environment of the DEMO breeding blanket, along with subsequent post-irradiation examinations (PIEs) of irradiated beryllium-based ...
Vladimir Chakin +15 more
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Growth of multifractal tungsten nanostructure by He bubble induced directional swelling
New Journal of Physics, 2015 Helium (He) plasma irradiation to tungsten (W) leads to morphology changes in nanometer scale by the formation and growth of He bubbles. Initially pinholes and protrusions are formed on the surface followed by the formation of nanostructures.
Shin Kajita +3 more
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Service life evaluation of rigid explosive transfer lines [PDF]
This paper describes a joint Army/NASA-sponsored research program on the service life evaluation of rigid explosive transfer lines. These transfer lines are used to initiate emergency crew escape functions on a wide variety of military and NASA aircraft.
Bement, L. J. +2 more
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Requirements for long-life operation of inert gas hollow cathodes: Preliminary report [PDF]
An experimental investigation was initiated to establish conditioning procedures for reliable hollow cathode operation via the characterization of critical parameters in a representative cathode test facility.
Macrae, Gregory S., Verhey, Timothy R.
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Ion Irradiation Effect of Austenitic Steels and Ferritic-Martensitic Steels [PDF]
, 2015 奥氏体不锈钢被广泛地用于当前的商业沸水堆、压水堆和部分快堆的堆芯及其附属结构材料。铁素体-马氏体钢是高剂量反应堆结构候选材料，比如用于聚变堆的第一壁材料，以及快堆的燃料包壳及管道。与奥氏体不锈钢相比，铁素体-马氏体钢最明显的优势就是其较高的抗辐照肿胀能力。低活化铁素体-马氏体钢降低或消除了一些长衰变元素，降低了材料的活性，使其在相对短的时间内完成衰变，便于退役后浅埋废料。为了研究奥氏体钢和铁素体-马氏体钢的辐照性能，并探究辐照温度、注He浓度、辐照剂量等对其辐照效应的影响，本论文对奥氏体不锈钢304 ...
王旭
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Nuclear FusionExploring novel plasma-facing materials with exceptional irradiation resistance is a pivotal and challenging endeavor for applications in the harsh environment of energetic ion irradiation in future fusion reactors.
Guo Pu +14 more
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Advanced-power-reactor design concepts and performance characteristics [PDF]
Five reactor cooling concepts which allow continued reactor operation following a single rupture of the coolant system are presented for application with the APR.
Davison, H. W. +3 more
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, 2012 A high energy beam absorber has been built for the Advanced Superconducting Test Accelerator (ASTA) at Fermilab. In the facility's initial configuration, an electron beam will be accelerated through 3 TTF-type or ILC-type RF cryomodules to an energy of ...
Baffes, C. +4 more
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