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    FAST NEUTRON REACTOR AND NEUTRON REFLECTOR BLOCK OF A FAST NEUTRON REACTOR
    2.
    发明公开
    FAST NEUTRON REACTOR AND NEUTRON REFLECTOR BLOCK OF A FAST NEUTRON REACTOR 审中-公开
    新生儿中枢神经系统中枢神经系统中枢神经系统

    公开(公告)号：EP3082132A1

    公开(公告)日：2016-10-19

    申请号：EP14869046.4

    申请日：2014-12-08

    申请人： Joint Stock Company "Akme-Engineering"

    发明人： BULAVKIN, Sergey Viktorovich

    IPC分类号： G21C11/06 ,  G21C15/10

    CPC分类号： G21C15/10 ,  G21C1/02 ,  G21C11/06 ,  G21C15/28 ,  G21Y2004/302 ,  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一个由重液态金属冷却的燃料棒组成的核心，以及设置在芯体周围的中子反射块，它包括一个在外壳上方的至少一个入口开口的钢壳体， 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，已经穿过其中的上部和下部边界的转向冷却剂流通过该入口开口 芯，进入套管的底部; 而且，在外壳的外侧，在入口开口的上方还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。

    DRIVE OF AN EMERGENCY SAFETY ROD
    3.
    发明公开
    DRIVE OF AN EMERGENCY SAFETY ROD 审中-公开
    ANTRIEB EINER NOTFALLSICHERHEITSSTANGE

    公开(公告)号：EP3065138A1

    公开(公告)日：2016-09-07

    申请号：EP14858485.7

    申请日：2014-04-18

    申请人： Joint Stock Company "Akme-Engineering"

    发明人： VAKHRUSHIN, Mikhail Petrovich ,  GOLOVIN, Ivan Aleksandrovich ,  PODIN, Aleksey Ivanovich ,  USMANOV, Anton Erikovich

    IPC分类号： G21C7/12

    CPC分类号： G21C7/14 ,  G21Y2004/30 ,  H02K7/106 ,  H02K7/11 ,  H02K7/116 ,  H02K11/21 ,  Y02E30/34 ,  Y02E30/39

    摘要： The invention relates to nuclear technology, and specifically to 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. The invention makes it possible to reduce the time necessary for adding negative reactivity to a nuclear reactor core.

    摘要翻译： 本发明涉及核技术，特别涉及用于控制和保护核反应堆的系统。 核反应堆的紧急安全杆的驱动器包括电驱动器，减速齿轮和齿条齿轮。 电动驱动器包含基于永磁体的非接触电动机，其安装在具有电动机转子位置传感器的电动驱动器的壳体中，以及用于改变电动驱动器的旋转速率的减速装置。 为了提供连接到其上的系统吸收杆的往复运动，齿条与齿条齿轮的轴线安装有齿条。 具有非接触电流源的齿形电磁离合器安装在齿条和小齿轮的内轴上，能够实现半联轴器的刚性和同时的机械联接，并且驱动器包含反向运动联轴器，齿条分离弹簧 和齿条位置传感器。 本发明使得可以减少向核反应堆芯增加负反应性所需的时间。

    METHOD FOR GUARANTEEING FAST REACTOR CORE SUBCRITICALITY UNDER CONDITIONS OF UNCERTAINTY REGARDING THE NEUTRON-PHYSICAL CHARACTERISTICS THEREOF
    6.
    发明公开
    METHOD FOR GUARANTEEING FAST REACTOR CORE SUBCRITICALITY UNDER CONDITIONS OF UNCERTAINTY REGARDING THE NEUTRON-PHYSICAL CHARACTERISTICS THEREOF 审中-公开
    的程序对中子物理特征物的不安全状态，确保更快REAKTORKERNSUBKRITIKALITÄT

    公开(公告)号：EP3065137A1

    公开(公告)日：2016-09-07

    申请号：EP14856854.6

    申请日：2014-03-19

    申请人： Joint Stock Company "Akme-Engineering"

    发明人： MELNIKOV, Kirill Gennadievich ,  TORMYSHEV, Ivan Vladimirovich ,  SHARIKPULOV, Said Mirfaisovich ,  BULAVKIN, Sergey Viktorovich ,  FILIN, Aleksandr Ivanovich ,  BOROVITSKY, Stepan Artemovich

    IPC分类号： G21C7/08

    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： 一种用于不确定的情况下保障快中子反应堆芯次临界方法包括，在组装反应堆芯，导电芯电抗器的次临界物理测量和比较设计值获得的特征之后; 然后，如果存在的所获得的特征值和设计值之间的差异，在反应堆堆芯的燃料部分的电平在反应器中安装可调节的反应性棒，worin可调的硼-B10同位素富集水平 反应性杆被选择为比补偿电抗器芯的棒的硼-B10同位素富集水平。 技术结果besteht在提高吸收棒的补偿组的元素，省去了提高其移动，简化了生产过程中使用的监测技术，并简化安全反应堆控制算法的操作条件。

    NUCLEAR FUEL PELLET HAVING ENHANCED THERMAL CONDUCTIVITY, AND PREPARATION METHOD THEREOF
    9.
    发明公开
    NUCLEAR FUEL PELLET HAVING ENHANCED THERMAL CONDUCTIVITY, AND PREPARATION METHOD THEREOF 审中-公开
    具有产生改进的导电性和工艺核燃料片剂

    公开(公告)号：EP3076398A1

    公开(公告)日：2016-10-05

    申请号：EP14865710.9

    申请日：2014-11-21

    申请人： Joint Stock Company "Akme-Engineering"

    发明人： KURINA, Irina Semyonovna ,  POPOV, Vjacheslav Vasilyevich ,  RUMYANTSEV, Vladimir Nikolaevich ,  RUSANOV, Aleksander Evgenievich ,  ROGOV, Stepan Sergeevich ,  SHARIKPULOV, Said Mirfaisovich

    IPC分类号： G21C3/58

    CPC分类号： G21C3/623 ,  G21C3/044 ,  G21C3/58 ,  G21C21/02 ,  G21C2003/045 ,  Y02E30/38

    摘要： 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°C, sintering is carried out in an insignificant amount of liquid phase at a temperature ranging between 1600 and 2200°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.

    FUEL ROD CLADDING, FUEL ROD AND FUEL ASSEMBLY
    10.
    发明公开
    FUEL ROD CLADDING, FUEL ROD AND FUEL ASSEMBLY 有权
    BRENNSTABHÜLLE，BRENNSTAB UND BRENNSTOFFANORDNUNG

    公开(公告)号：EP3076397A1

    公开(公告)日：2016-10-05

    申请号：EP14864912.2

    申请日：2014-06-03

    申请人： Joint Stock Company "Akme-Engineering"

    发明人： DERUNOV, Viacheslav Vasilievich ,  MAYOROV, Viktor Mihailovich ,  POMESCHIKOV, Pavel Andreevich ,  RUSANOV, Aleksander Evgenievich ,  SMIRNOV, Aleksandr Alekseevich ,  SHULEPIN, Sergey Viktorovich ,  SHARIKPULOV, Said Mirfaisovich

    IPC分类号： G21C3/02 ,  G21C3/08 ,  G21C3/30

    CPC分类号： G21C3/08 ,  G21C1/03 ,  G21C3/04 ,  G21C3/07 ,  G21C3/12 ,  G21C3/30 ,  G21C21/02 ,  Y02E30/40

    摘要： 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 cladding of a fuel rod for a heavy liquid metal cooled reactor is in the form of a weldless tubular element with 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 40º (preferably from 30 to 40º) 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.

    摘要翻译： 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，并且还可用于制造燃料棒模拟器，其用于设计用于测试真实的可操作性的照射装置 燃料组件 用于重液态金属冷却反应器的燃料棒的现有包层是无焊接管状元件的形式，其中螺旋形螺旋翅片设置在所述元件的外表面上，该铁芯由铁素体 - 马氏体铬硅钢制成， 在GOST 5639刻度上的最小铁素体晶粒尺寸为7，其中每个翅片具有22至40度（优选30至40度）的开度角，并且翅片的横截面呈梯形，具有圆角 在梯形顶部的梯形和平滑的角落在梯形的基地。 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由于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而导致燃料棒和组件的性能特性的改进。