SERVICEABILITY OF THE FUEL ELEMENTS IN A VK-50 BOILING-WATER VESSEL REACTOR

A. S. Kurskiy; I. M. Smirnova; G. V. Filiakin; I.I. Semidotskiy; G. P. Kobilyanskiy; V. K. Shamardin

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SERVICEABILITY OF THE FUEL ELEMENTS IN A VK-50 BOILING-WATER VESSEL REACTOR

机译：VK-50沸水容器反应器中燃料元素的可维修性

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The results of physical-metallurgical studies of fuel-element cladding in a nuclear power plant with a boiling-water vessel reactor are presented. It is shown that the fuel materials are highly reliable under the operating conditions.

机译：提出了具有沸水容器反应堆的核电站中燃料元素包壳的物理冶金研究结果。结果表明，燃料材料在工作条件下是高度可靠的。

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来源
《Atomic Energy》 |2013年第2期|95-101|共7页
作者
A. S. Kurskiy; I. M. Smirnova; G. V. Filiakin; I.I. Semidotskiy; G. P. Kobilyanskiy; V. K. Shamardin;
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作者单位

State Science Center - Research Institute for Atomic Reactors (GNTs NIIAR), Dimitrovgrad;

State Science Center - Research Institute for Atomic Reactors (GNTs NIIAR), Dimitrovgrad;

State Science Center - Research Institute for Atomic Reactors (GNTs NIIAR), Dimitrovgrad;

State Science Center - Research Institute for Atomic Reactors (GNTs NIIAR), Dimitrovgrad;

State Science Center - Research Institute for Atomic Reactors (GNTs NIIAR), Dimitrovgrad;

State Science Center - Research Institute for Atomic Reactors (GNTs NIIAR), Dimitrovgrad;

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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
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入库时间 2022-08-18 00:39:41

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1. COOLANT RADIOLYSIS AND HYDROGEN EXPLOSION PROTECTION FOR THE VK-50 BOILING-WATER REACTOR VESSEL [J] . A. S. Kurskii Atomic Energy . 2014,第5期

机译：VK-50沸水反应堆容器的冷却液放射性和氢爆炸防护
2. CORROSION DAMAGE TO Kh18N9T STEEL AFTER 25 YEARS OF OPERATION IN THE STEAM-WATER MEDIUM OF A VK-50 BOILING-WATER REACTOR [J] . G. V. Filyakin, V. K. Shamardin, Yu. D. Goncharenko Atomic Energy . 2006,第1期

机译：在VK-50沸水反应堆的汽水介质中运行25年后，对Kh18N9T钢的腐蚀损害
3. SAFETY VALIDATION OF THE VK-50 BOILING WATER VESSEL REACTOR WITH LARGE COOLANT LEAKS [J] . A. S. Kurskii Atomic Energy . 2014,第2期

机译：大泄漏冷却液的VK-50开水容器反应器的安全性验证
4. A 2-D CORRELATION TO EVALUATE FUEL-CLADDING GAP THERMAL CONDUCTANCE IN MIXED OXIDE FUEL ELEMENTS FOR SODIUM-COOLED FAST REACTORS [C] . Lavarenne J., Bubelis E., Davies U., International Nuclear Fuel Cycle Conference . 2019

机译：一种二维相关性，以评估混合氧化物燃料元件中的燃料包层燃料旋转热传导钠冷却的快速反应器
5. Estimate of radiation-induced steel embrittlement in the BWR core shroud and vessel wall from reactor-grade MOX/UOX fuel for the nuclear power plant at Laguna Verde, Veracruz, Mexico. [D] . Vickers, Lisa Rene. 2001

机译：墨西哥韦拉克鲁斯州拉古纳维德核电站的反应堆级MOX / UOX燃料估算了BWR堆芯护罩和容器壁中辐射诱发的钢脆性。
6. Analysis of the Secondary Phases Formed by Corrosion of U3Si2-Al Research Reactor Fuel Elements in the Presence of Chloride Rich Brines [O] . Andreas Neumann, Martina Klinkenberg, Hildegard Curtius 2018

机译：富氯化物存在下U3Si2-Al研究堆燃料元素腐蚀形成的第二相的分析
7. Feasibility of underwater welding of highly irradiated in-vessel components of boiling-water reactors: A literature review [O] . Lund, A.L. 1997

机译：沸水反应堆高度辐照的容器内部件水下焊接的可行性：文献综述
8. STUDY OF A PRESTRESSED CONCRETE VESSEL FOR A BOILING-WATER REACTOR OF 1000 MWE. [R] . 1967

机译：1000 mWE沸水反应堆预应力混凝土容器的研究。

SERVICEABILITY OF THE FUEL ELEMENTS IN A VK-50 BOILING-WATER VESSEL REACTOR

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