Decommissioning industrial uranium-graphite reactors

I. D. Kulikov; V. D. Safutin; V. M. Simanovskii

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Decommissioning industrial uranium-graphite reactors

机译：使工业铀-石墨反应堆退役

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The basic problems in decommissioning industrial uranium-graphite reactors are analyzed, taking account of experience in decommissioning the I-1 and EI-2 reactors at the Siberian Chemical Combine. On the basis of the analysis, decommissioning with delayed dismantling of the reactor structures is recommended.

机译：考虑到西伯利亚化学联合工厂I-1和EI-2反应堆退役的经验，分析了工业铀-石墨反应堆退役的基本问题。在分析的基础上，建议退役并延迟拆除反应堆结构。

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来源
《Atomic Energy》 |1999年第2期|p.569-576|共8页
作者
I. D. Kulikov; V. D. Safutin; V. M. Simanovskii;
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收录信息美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
原文格式 PDF
正文语种 eng
中图分类原子能技术;
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入库时间 2022-08-18 00:39:58

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专利

1. Decommissioning of uranium-graphite reactors [J] . S.E.Skorodumov, V.N.Ezhov, V.V.Plekhanov Transactions of the American nuclear society . 2013,第juna期

机译：铀-石墨反应堆退役
2. RADIATION CHARACTERISTICS OF GRAPHITE IN THE COMMERCIAL URANIUM-GRAPHITE REACTORS AT THE MAYAK INDUSTRIAL ASSOCIATION [J] . M. P. Tsevelev, A. B. Kutuzov, S. V. Korenev, Atomic Energy . 2004,第1期

机译：玛雅克工业协会商业铀-石墨反应器中石墨的辐射特性
3. Fabrication and calibration of new carbon-14 reference standards using irradiated graphite from uranium-graphite reactors [J] . A.O. Pavliuk, S.G. Kotlyarevsky, R.I. Kan, Nuclear Instruments & Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment . 2021,第Jula1期

机译：用铀 - 石墨反应器辐照石墨制备和校准新的碳-14参考标准
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. Environmental monitoring and dose assessment for a decommissioned reactor, SEFOR, and a radioactive waste disposal site, Harmon Road. [D] . Lee, Yew Loon. 1989

机译：SEFOR退役反应堆和Harmon Road放射性废物处置场的环境监测和剂量评估。
6. Visual Locating of Reactor in an Industrial Environment Using the Composite Method [O] . Chenguang Cao, Qi Ouyang, Jiamu Hou, 2020

机译：使用复合方法的工业环境中反应堆的可视化定位
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

Decommissioning industrial uranium-graphite reactors

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