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About chemical form and binding energy of 14c in irradiated graphite of uranium graphite nuclear reactors

机译：关于铀石墨核反应堆辐照石墨14℃的化学形式和结合能

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Evgeny Vladimirovich Bespala; Alexander Olegovich Pavliuk; Vladimir Sergeevich Zagumennov; Sergey Gennad’evich Kotlyarevskiy;
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1. ELECTROCHEMICAL DECONTAMINATION OF IRRADIATED NUCLEAR GRAPHITE OF URANIUM-GRAPHITE NUCLEAR REACTORS [J] . Pavlyuk A. O., Bespala E. V., Kotlyarevskii S. G., Atomic Energy . 2020,第1期

机译：铀 - 石墨核反应堆辐照核石墨电化学净化
2. Radionuclides in Irradiated Graphite of Industrial Uranium–Graphite Reactors: Effect of Irradiation and Thermochemical Treatment on the Graphite Structure [J] . A. A. Shiryaev, A. G. Volkova, E. V. Zakharova, Radiochemistry . 2018,第6期

机译：辐照核酸核核酸石墨 - 石墨反应器的辐射核素：辐照和热化学处理对石墨结构的影响
3. Radionuclides in Irradiated Graphite of Uranium–Graphite Reactors: Decontamination by Thermochemical Methods [J] . A. G. Volkova, E. V. Zakharova, N. I. Rodygina, Radiochemistry . 2018,第6期

机译：铀 - 石墨反应器辐照石墨中的放射性核素：通过热化学方法去污
4. Capability assessment for application of clay mixture as barrier material for irradiated zirconium alloy structure elements long-term processing for storage during decommissioning of uranium-graphite nuclear reactors [C] . S G Kotlyarevskiy, A O Pavliuk, E V Zakharova International Scientific Conference "Issues of Physics and Technology in Science, Industry and Medicine" . 2016

机译：在铀 - 石墨核反应堆退役期间，粘土混合物作为辐射锆合金结构元件的屏障材料作为辐射锆合金结构元件的长期加工的能力评估
5. Characterization of 14C in Neutron-Irradiated Graphite. [D] . LaBrier, Daniel Patrick. 2013

机译：中子辐照石墨中14 C的表征。
6. The Impact of Alkaliphilic Biofilm Formation on the Release and Retention of Carbon Isotopes from Nuclear Reactor Graphite [O] . S. P. Rout, L. Payne, S. Walker, -1

机译：嗜碱生物膜的形成对核反应堆石墨中碳同位素的释放和保留的影响
7. Capability assessment for application of clay mixture as barrier material for irradiated zirconium alloy structure elements long-term processing for storage during decommissioning of uranium-graphite nuclear reactors [O] . S G Kotlyarevskiy, A O Pavliuk, E V Zakharova, 2016

机译：在铀 - 石墨核反应堆退役期间，粘土混合物作为辐射锆合金结构元件的屏障材料作为辐射锆合金结构元件的长期加工的能力评估
8. REACTOR IRRADIATION OF URANIUM-IMPREGNATED GRAPHITE AT 1500°C TO 10% BURNUP [R] . P. J. Peterson, J. A. Leary, W. J. Maraman 1963

机译：铀浸渍石墨在1500°C至10％燃烧下的反应器辐照

About chemical form and binding energy of 14c in irradiated graphite of uranium graphite nuclear reactors

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