公开(公告)号：US20160232994A1

公开(公告)日：2016-08-11

申请号：US15022689

申请日：2014-03-19

Applicant: JOINT STOCK COMPANY "AKME-ENGINEERING"

Inventor： Kirill Gennadievich Melnikov ,  Ivan Vladimirovich Tormyshev ,  Said Mirfaisovich Sharikpulov ,  Sergey Viktorovich Bulavkin ,  Aleksandr Ivanovich Filin ,  Stepan Artemovich Borovitsky

IPC: G21C7/08 ,  G21C21/18

CPC classification number: G21C7/08 ,  G21C9/02 ,  G21C11/00 ,  G21C11/06 ,  G21C21/18 ,  Y02E30/34 ,  Y02E30/39

Abstract: 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.

Abstract translation: 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。

公开(公告)号：US10037822B2

公开(公告)日：2018-07-31

申请号：US15022834

申请日：2014-03-19

Applicant: Joint Stock Company “AKME-Engineering”

Inventor： 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: G21C1/03 ,  G21C13/08 ,  G21C21/00 ,  C23C22/72 ,  C23C22/73 ,  G21C15/247 ,  G21C17/022

CPC classification number: G21C1/03 ,  C23C22/72 ,  C23C22/73 ,  G21C13/08 ,  G21C15/247 ,  G21C17/0225 ,  G21C21/00 ,  Y02E30/40

Abstract: 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.

公开(公告)号：US10381119B2

公开(公告)日：2019-08-13

申请号：US15021618

申请日：2014-11-21

Applicant: Joint Stock Company “AKME-Engineering”

Inventor： Irina Semyonovna Kurina ,  Vjacheslav Vasilyevich Popov ,  Vladimir Nikolaevich Rumyantsev ,  Aleksander Evgenievich Rusanov ,  Stepan Sergeevich Rogov ,  Said Mirfaisovich Sharikpulov

IPC: G21C3/62 ,  G21C21/02 ,  G21C3/04 ,  G21C3/58

Abstract: The invention relates to nuclear physics, and specifically to reactor fuel elements and units thereof, and particularly to the composition of solid ceramic fuel elements based on uranium dioxide, intended for and exhibiting characteristics for being used in variously-purposed nuclear reactors. The result consists in a more reliable, special structure and a simple composition of uranium dioxide without heterogeneous fuel pellet additives, approaching the characteristics of a monocrystal having enhanced, and specifically exceeding reference data, thermal conductivity as temperature increases, and a simple production method thereof. The result is achieved in that pores of between 1 and 5 microns in size are distributed along the perimeters of grains in the micro-structure of each metal cluster in a nuclear fuel pellet, and in that located within the grains are pores which are predominantly nano-sized. In addition, the metal clusters comprise between 0.01 and 1.0 percent by mass. The invention provides for a method of preparing a nuclear fuel pellet, including precipitating metal hydroxides, in two stages, having different pH levels. Uranium metal is melted at a temperature exceeding 1150 DEG C., sintering is carried out in an insignificant amount of liquid phase at a temperature ranging between 1600 and 2200 DEG C. in a hydrogen medium until forming uranium dioxide, the structure of which includes metal clusters dispersed therein. An X-ray photon spectroscope is used for identifying the new structure of the UO2 pellet and the additional U—U chemical bond.

公开(公告)号：US20160232993A1

公开(公告)日：2016-08-11

申请号：US15021618

申请日：2014-11-21

Applicant: JOINT STOCK COMPANY "AKME-ENGINEERING"

Inventor： Irina Semyonovna Kurina ,  Vjacheslav Vasilyevich Popov ,  Vladimir Nikolaevich Rumyantsev ,  Aleksander Evgenievich Rusanov ,  Stepan Sergeevich Rogov ,  Said Mirfaisovich Sharikpulov

IPC: G21C3/62 ,  G21C21/02

CPC classification number: G21C3/623 ,  G21C3/044 ,  G21C3/045 ,  G21C3/58 ,  G21C21/02 ,  Y02E30/38

Abstract: The invention relates to nuclear physics, and specifically to reactor fuel elements and units thereof, and particularly to the composition of solid ceramic fuel elements based on uranium dioxide, intended for and exhibiting characteristics for being used in variously-purposed nuclear reactors. The result consists in a more reliable, special structure and a simple composition of uranium dioxide without heterogeneous fuel pellet additives, approaching the characteristics of a monocrystal having enhanced, and specifically exceeding reference data, thermal conductivity as temperature increases, and a simple production method thereof. The result is achieved in that pores of between 1 and 5 microns in size are distributed along the perimeters of grains in the micro-structure of each metal cluster in a nuclear fuel pellet, and in that located within the grains are pores which are predominantly nano-sized. In addition, the metal clusters comprise between 0.01 and 1.0 percent by mass. The invention provides for a method of preparing a nuclear fuel pellet, including precipitating metal hydroxides, in two stages, having different pH levels. Uranium metal is melted at a temperature exceeding 1150 DEG C., sintering is carried out in an insignificant amount of liquid phase at a temperature ranging between 1600 and 2200 DEG C. in a hydrogen medium until forming uranium dioxide, the structure of which includes metal clusters dispersed therein. An X-ray photon spectroscope is used for identifying the new structure of the UO2 pellet and the additional U—U chemical bond.

Abstract translation: 本发明涉及核物理学，具体涉及反应堆燃料元件及其单元，特别涉及用于各种目的的核反应堆中用于和表现出特性的基于二氧化铀的固体陶瓷燃料元件的组成。 其结果在于具有更可靠，特殊的结构和简单的组成的无异质燃料颗粒添加剂的二氧化铀，接近具有增强的特性，特别是超过参考数据的温度升高时的热导率，以及简单的生产方法 。 结果是通过在核燃料颗粒中的每个金属簇的微结构中的颗粒周长分布尺寸为1至5微米的孔分布，并且位于颗粒内的孔是主要为纳米的孔 尺寸。 另外，金属簇的含量为0.01〜1.0质量％。 本发明提供了一种制备核燃料颗粒的方法，其包括在两个阶段中析出具有不同pH值的金属氢氧化物。 铀金属在超过1150℃的温度下熔化，在氢气介质中在1600至2200℃的温度范围内以不显着量的液相进行烧结，直到形成二氧化铀，其结构包括金属 分散在其中的簇。 使用X射线光子分光镜来识别UO2颗粒的新结构和附加的U-U化学键。

公开(公告)号：US10720244B2

公开(公告)日：2020-07-21

申请号：US15021698

申请日：2014-06-03

Applicant: Joint Stock Company “AKME-Engineering”

Inventor： Viacheslav Vasilievich Derunov ,  Viktor Mihailovich Mayorov ,  Pavel Andreevich Pomeschikov ,  Aleksander Evgenievich Rusanov ,  Aleksandr Alekseevich Smirnov ,  Sergey Viktorovich Shulepin ,  Said Mirfaisovich Sharikpulov

IPC: G21C3/06 ,  G21C3/08 ,  G21C3/07 ,  G21C1/03 ,  G21C3/12 ,  G21C3/04 ,  G21C21/02 ,  G21C3/30

Abstract: Systems for controlling and protecting nuclear reactors. A drive of an emergency safety rod of a nuclear reactor includes an electric drive, a reduction gear, and a rack-and-pinion gear. The electric drive contains a contactless electric motor based on permanent magnets, which is installed in the housing of the electric drive with a motor rotor position sensor, and a reduction gear for changing the rate of rotation of the electric drive. A toothed rack is installed along the axis of the rack-and-pinion gear in order to provide for the reciprocating motion of a system absorber rod connected thereto. A toothed electromagnetic clutch having a contactless current supply is installed on an inner shaft of the rack-and-pinion gear, enabling the rigid and simultaneous mechanical coupling of half-couplings, and the drive contains a reverse-motion coupling, a rack-separation spring and toothed rack position sensors.

公开(公告)号：US10573417B2

公开(公告)日：2020-02-25

申请号：US15022689

申请日：2014-03-19

Applicant: Joint Stock Company “AKME-Engineering”

Inventor： Kirill Gennadievich Melnikov ,  Ivan Vladimirovich Tormyshev ,  Said Mirfaisovich Sharikpulov ,  Sergey Viktorovich Bulavkin ,  Aleksandr Ivanovich Filin ,  Stepan Artemovich Borovitsky

IPC: G21C7/06 ,  G21C7/08 ,  G21C9/02 ,  G21C11/06 ,  G21C21/18 ,  G21C11/00

Abstract: 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.

公开(公告)号：US10204712B2

公开(公告)日：2019-02-12

申请号：US15102350

申请日：2014-12-08

Applicant: Joint Stock Company “AKME-Engineering”

Inventor： 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: C23C22/72 ,  G21C13/087 ,  C23C22/73 ,  G21C17/022 ,  C23C8/10

Abstract: 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.

公开(公告)号：US20170018319A1

公开(公告)日：2017-01-19

申请号：US15102350

申请日：2014-12-08

Applicant: JOINT STOCK COMPANY "AKME-ENGINEERING"

Inventor： 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: G21C13/087 ,  C23C22/73

CPC classification number: G21C13/087 ,  C23C22/73 ,  G21C17/0225 ,  G21Y2002/103 ,  G21Y2004/20 ,  Y02E30/40

Abstract: 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.

Abstract translation: 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。

公开(公告)号：US20160225468A1

公开(公告)日：2016-08-04

申请号：US15021698

申请日：2014-06-03

Applicant: JOINT STOCK COMPANY "AKME-ENGINEERING"

Inventor： Viacheslav Vasilievich Derunov ,  Viktor Mihailovich Mayorov ,  Pavel Andreevich Pomeschikov ,  Aleksander Evgenievich Rusanov ,  Aleksandr Alekseevich Smirnov ,  Sergey Viktorovich Shulepin ,  Said Mirfaisovich Sharikpulov

IPC: G21C3/08 ,  G21C3/12 ,  G21C3/07 ,  G21C1/03

Abstract: The invention relates to the field of nuclear engineering and can be used in the manufacture of fuel rods and fuel assemblies for heavy liquid metal cooled reactors, and also in the manufacture of fuel rod simulators for use in irradiation devices designed to test the operability of real fuel assemblies. The present gadding of a fuel rod for a heavy liquid metal cooled reactor is in the form of a weldless tubular element h helically-coiled fins disposed on the outer surface of said element, which is made from a ferritic-martensitic chromium-silicon steel with a minimum ferrite grain size of 7 on the GOST 5639 scale, wherein each fin has an opening angle of from 22 to 40 (preferably from 30 to 40) and the cross-section of the fin is in the shape of a trapezoid with rounded corners at the top of the trapezoid and smooth corners at the base of the trapezoid. Also disclosed are a fuel rod comprising the above cladding, and a fuel assembly. The technical result of the invention is an improvement in the performance characteristics of fuel rods and assemblies as a result of the long-term resistance of the cladding in the environment of a heavy liquid metal coolant such as lead or a eutectic of lead and bismuth.

Abstract translation: 本发明涉及核工程领域，并且可用于制造用于重液态金属冷却反应器的燃料棒和燃料组件，并且还可用于制造用于测试真实可操作性的照射装置的燃料棒模拟器 燃料组件 用于重液态金属冷却反应器的燃料棒的当前装配是无弧管状元件的形式，h是螺旋形螺旋翅片，其设置在所述元件的外表面上，所述翅片由铁素体 - 马氏体铬硅钢制成， 在GOST 5639标尺上的最小铁素体晶粒尺寸为7，其中每个翅片的开度为22至40（优选为30至40），并且翅片的横截面为具有圆角的梯形 在梯形的底部的梯形和平滑的角落的顶部。 还公开了包括上述包层和燃料组件的燃料棒。 本发明的技术结果是燃料棒和组件的性能特性得到改善，这是由于在诸如铅或铅和铋的共晶体的重液态金属冷却剂的环境中包层的长期阻力。