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1. 发明授权

US10037822B2 Method for the in situ passivation of the steel surfaces of a nuclear reactor 有权
公开(公告)号：US10037822B2
公开(公告)日：2018-07-31
申请号：US15022834
申请日：2014-03-19
申请人： Joint Stock Company “AKME-Engineering”
发明人： Petr Nikiforovich Martynov , Radomir Shamilievich Askhadullin , Konstantin Dmitrievich Ivanov , Aleksandr Urievich Legkikh , Aleksey Nikolaevich Storozhenko , Aleksandr Ivanovich Filin , Sergey Viktorovich Bulavkin , Said Mirfaisovich Sharikpulov , Stepan Artemovich Borovitsky
IPC分类号： G21C1/03 , G21C13/08 , G21C21/00 , C23C22/72 , C23C22/73 , G21C15/247 , G21C17/022
CPC分类号： G21C1/03 , C23C22/72 , C23C22/73 , G21C13/08 , G21C15/247 , G21C17/0225 , G21C21/00 , Y02E30/40
摘要： The invention relates to the field of nuclear technology, and specifically to a method for the in situ passivation of steel surfaces. The method consists in installing, in a position intended for a regular core, a core simulator in the form of a model of the core, which models the shape thereof, the relative position of the core components, and also the mass characteristics thereof; next, the reactor is filled with a heavy liquid metal heat transfer medium, the heat transfer medium is heated to a temperature which provides for the conditions of passivation, and in situ passivation is carried out in two stages, the first of which includes an isothermal passivation mode in conformity with the conditions determined for this stage, and the second mode includes non-isothermal passivation, which is carried out under different conditions, after which the core simulator is removed and the regular core is installed in the place thereof. The method provides for the corrosion-resistance of steel elements in a heavy liquid metal heat transfer medium environment and permits a decrease in the maximum rate of oxygen consumption during the initial period of operation of a nuclear actor.

2. 发明申请

US20170018320A1 Fast Neutron Reactor and Neutron Reflector Block of a Fast Neutron Reactor 审中-公开
标题翻译：快中子反应堆快中子反应堆和中子反射块
公开(公告)号：US20170018320A1
公开(公告)日：2017-01-19
申请号：US15102445
申请日：2014-12-08
申请人： Joint Stock Company "AKME-Engineering"
发明人： Sergey Viktorovich Bulavkin
IPC分类号： G21C15/10 , G21C11/06 , G21C15/28 , G21C1/02
CPC分类号： G21C15/10 , G21C1/02 , G21C11/06 , G21C15/28 , Y02E30/34 , Y02E30/35
摘要： The invention relates to the field of nuclear engineering, and more particularly to designs for removable neutron reflector blocks for heavy liquid metal-cooled fast neutron reactors. The present fast neutron reactor contains a core consisting of heavy liquid metal-cooled fuel rods, and neutron reflector blocks, disposed around the core, which comprise a steel casing with at least one inlet opening in the side walls thereof above the core boundary, said inlet opening being intended for diverting part of the coolant flow from the space between the blocks into the casing, and at least one vertical pipe mounted in the casing, through which the diverted coolant flow, which has passed through the upper and lower boundaries of the core, enters the bottom part of the casing; also, on the outer side of the casing, above the inlet opening, there is mounted a throttling device for creating hydraulic resistance to the coolant flow in the space between the blocks. The technical result is an increase in the operating safety and the performance of a fast neutron reactor and a reduction in the heat exchange surface of the steam generator.
摘要翻译：本发明涉及核工程领域，更具体地涉及用于重液态金属冷却快中子反应堆的可移除中子反射块的设计。本发明的快中子反应堆包含由重液态金属冷却的燃料棒组成的核心和设置在芯体周围的中子反射器块，该中子反射块包括一个在壳体边界上方的侧壁中具有至少一个入口的钢壳体，入口开口旨在将冷却剂流的一部分从块之间的空间转移到壳体中，以及安装在壳体中的至少一个垂直管，通过该垂直管已经通过了转向冷却剂流的上部和下部边界芯，进入套管的底部; 另外，在外壳的外侧，在入口开口的上方，安装有用于在块之间的空间中产生对冷却剂流的液压阻力的节流装置。技术结果是增加了快中子反应器的运行安全性和性能，并减少了蒸汽发生器的热交换面。

3. 发明申请

US20160232994A1 METHOD FOR GUARANTEEING FAST REACTOR CORE SUBCRITICALITY UNDER CONDITIONS OF UNCERTAINTY REGARDING THE NEUTRON-PHYSICAL CHARACTERISTICS THEREOF 审中-公开
标题翻译：在不确定条件下保证快速反应器核心亚临界的方法关于其中性物理特性的方法
公开(公告)号：US20160232994A1
公开(公告)日：2016-08-11
申请号：US15022689
申请日：2014-03-19
申请人： JOINT STOCK COMPANY "AKME-ENGINEERING"
发明人： Kirill Gennadievich Melnikov , Ivan Vladimirovich Tormyshev , Said Mirfaisovich Sharikpulov , Sergey Viktorovich Bulavkin , Aleksandr Ivanovich Filin , Stepan Artemovich Borovitsky
IPC分类号： G21C7/08 , G21C21/18
CPC分类号： G21C7/08 , G21C9/02 , G21C11/00 , G21C11/06 , G21C21/18 , Y02E30/34 , Y02E30/39
摘要： A method for guaranteeing fast reactor core subcriticality under conditions of uncertainty involves, after assembling the reactor core, conducting physical measurements of reactor core subcriticality and comparing the obtained characteristics with design values; then, if there is a discrepancy between the values of the obtained characteristics and the design values, installing adjustable reactivity rods in the reactor at the level of a fuel portion of the reactor core, wherein the level of boron-B10 isotope enrichment of the adjustable reactivity rods is selected to be higher than the level of boron-B10 isotope enrichment of compensating rods of the reactor core. The technical result consists in improving the operating conditions of absorbing elements of a compensating group of rods, eliminating the need for increasing the movement thereof, simplifying monitoring technologies used during production, and simplifying the algorithm for safe reactor control.
摘要翻译：在不确定性条件下保证快堆反应堆核心临界性的方法包括：组装反应堆堆芯后进行反应堆核心临界性的物理测量，并比较所获得的特征与设计值; 那么如果获得的特征值与设计值之间存在差异，则在反应堆的燃料部分的水平面上安装反应器中的可调节的反应性棒，其中可调整的硼-B10同位素浓度的水平选择反应性棒高于反应堆芯的补偿棒的硼-B10同位素富集水平。技术结果在于改善了补偿棒组吸收元件的运行条件，消除了增加其运动的需要，简化了生产过程中使用的监控技术，简化了安全反应堆控制算法。

4. 发明授权

US10573417B2 Method for guaranteeing fast reactor core subcriticality under conditions of uncertainty regarding the neutron-physical characteristics thereof 有权
公开(公告)号：US10573417B2
公开(公告)日：2020-02-25
申请号：US15022689
申请日：2014-03-19
申请人： Joint Stock Company “AKME-Engineering”
发明人： Kirill Gennadievich Melnikov , Ivan Vladimirovich Tormyshev , Said Mirfaisovich Sharikpulov , Sergey Viktorovich Bulavkin , Aleksandr Ivanovich Filin , Stepan Artemovich Borovitsky
IPC分类号： G21C7/06 , G21C7/08 , G21C9/02 , G21C11/06 , G21C21/18 , G21C11/00
摘要： A method for guaranteeing fast reactor core subcriticality under conditions of uncertainty involves, after assembling the reactor core, conducting physical measurements of reactor core subcriticality and comparing the obtained characteristics with design values; then, if there is a discrepancy between the values of the obtained characteristics and the design values, installing adjustable reactivity rods in the reactor at the level of a fuel portion of the reactor core, wherein the level of boron-B10 isotope enrichment of the adjustable reactivity rods is selected to be higher than the level of boron-B10 isotope enrichment of compensating rods of the reactor core. The technical result consists in improving the operating conditions of absorbing elements of a compensating group of rods, eliminating the need for increasing the movement thereof, simplifying monitoring technologies used during production, and simplifying the algorithm for safe reactor control.

5. 发明授权

US10204712B2 Method for inner-contour passivation of steel surfaces of nuclear reactor 有权
公开(公告)号：US10204712B2
公开(公告)日：2019-02-12
申请号：US15102350
申请日：2014-12-08
申请人： Joint Stock Company “AKME-Engineering”
发明人： Petr Nikiforovich Martynov , Radomir Shamilievich Askhadullin , Aleksey Nikolaevich Storozhenko , Konstantin Dmitrievich Ivanov , Aleksandr Urievich Legkikh , Said Mirfaisovich Sharikpulov , Aleksandr Ivanovich Filin , Sergey Viktorovich Bulavkin
IPC分类号： C23C22/72 , G21C13/087 , C23C22/73 , G21C17/022 , C23C8/10
摘要： A method for the inner-contour passivation of steel surfaces of a nuclear reactor consists in filling a first contour of a nuclear reactor with a liquid metal coolant, introducing a reagent into the liquid metal coolant, said reagent interacting with the material of elements of the first contour, forming a protective film, and heating the liquid metal coolant, having the reagent introduced therein, to a temperature allowing for conditions for forming the protective film. The liquid metal coolant having the reagent introduced therein is kept at said temperature until a continuous protective film is formed on the surface of the material of the elements of the first contour. The liquid metal coolant having reagent introduced therein is heated by means of the friction thereof against rotating vanes of a vane pump, which is submerged in the liquid metal coolant. The present invention thus provides for a simpler passivation process, a more reliable passivation mode, an increase in the safety thereof and a simpler control over the process of passivation of steel surfaces.

6. 发明申请

US20170018319A1 METHOD FOR INNER-CONTOUR PASSIVATION OF STEEL SURFACES OF NUCLEAR REACTOR 审中-公开
标题翻译：用于核反应堆钢表面钝化钝化的方法
公开(公告)号：US20170018319A1
公开(公告)日：2017-01-19
申请号：US15102350
申请日：2014-12-08
申请人： JOINT STOCK COMPANY "AKME-ENGINEERING"
发明人： Petr Nikiforovich Martynov , Radomir Shamilievich Askhadullin , Aleksey Nikolaevich Storozhenko , Konstantin Dmitrievich Ivanov , Aleksandr Urievich Legkikh , Said Mirfaisovich Sharikpulov , Aleksandr Ivanovich Filin , Sergey Viktorovich Bulavkin
IPC分类号： G21C13/087 , C23C22/73
CPC分类号： G21C13/087 , C23C22/73 , G21C17/0225 , G21Y2002/103 , G21Y2004/20 , Y02E30/40
摘要： A method for the inner-contour passivation of steel surfaces of a nuclear reactor consists in filling a first contour of a nuclear reactor with a liquid metal coolant, introducing a reagent into the liquid metal coolant, said reagent interacting with the material of elements of the first contour, forming a protective film, and heating the liquid metal coolant, having the reagent introduced therein, to a temperature allowing for conditions for forming the protective film. The liquid metal coolant having the reagent introduced therein is kept at said temperature until a continuous protective film is formed on the surface of the material of the elements of the first contour. The liquid metal coolant having reagent introduced therein is heated by means of the friction thereof against rotating vanes of a vane pump, which is submerged in the liquid metal coolant. The present invention thus provides for a simpler passivation process, a more reliable passivation mode, an increase in the safety thereof and a simpler control over the process of passivation of steel surfaces.
摘要翻译：用于核反应堆的钢表面的内轮廓钝化的方法包括用液态金属冷却剂填充核反应堆的第一轮廓，将试剂引入液态金属冷却剂中，所述试剂与元素的材料相互作用第一轮廓，形成保护膜，并且将其中引入有试剂的液态金属冷却剂加热至允许形成保护膜的条件的温度。将其中引入有试剂的液态金属冷却剂保持在所述温度，直到在第一轮廓的元件的材料的表面上形成连续的保护膜。引入其中的试剂的液态金属冷却剂借助于与浸没在液态金属冷却剂中的叶片泵的旋转叶片的摩擦而被加热。因此，本发明提供了更简单的钝化过程，更可靠的钝化模式，其安全性的增加以及对钢表面钝化过程的更简单的控制。

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