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    • 1. 发明公开
    • REACTOR SYSTEM WITH A LEAD-COOLED FAST REACTOR
    • REAKTORSYSTEM麻省理工EINEMBLEIGEKÜHLTENSCHNELLEN REAKTOR
    • EP3101658A4
    • 2017-09-20
    • EP14880808
    • 2014-11-27
    • STATE ATOMIC ENERGY CORP ROSATOM ON BEHALF OF THE RUSSIAN FEDERATION
    • KUBINTSEV BORIS BORISOVICHLEONOV VIKTOR NIKOLAEVICHLOPATKIN ALEKSANDR VIKTOROVICHCHERNOBROVKIN YURIY VASILIEVICH
    • G21C1/03F22B1/06G21C15/02G21C15/18G21C15/247G21C15/253G21C15/26G21C15/28
    • G21C15/18F22B1/063G21C1/03G21C15/02G21C15/247G21C15/253G21C15/26G21C15/28G21Y2002/50G21Y2004/302G21Y2004/40Y02E30/34Y02E30/35
    • The present invention relates to nuclear technology and is intended for use in power-generating systems with a fast reactor cooled by a liquid-metal coolant which is primarily in the form of molten lead or an alloy thereof. The problem addressed by the invention consists in reducing the specific volume of lead coolant per unit of power of the reactor and in increasing the safety of the reactor. The system comprises a reactor cavity (1) with an upper cover (2), an arranged within the cavity (1) reactor having an active zone (4), steam generators (5), circulation pumps (7), circulation conduits (8) and (9), actuating mechanism systems and devices for starting up, operating and shutting down the reactor system, wherein the steam generators (5) are in the form of tubular heat exchangers in which the lead coolant (10) flows within the pipes, while the water-steam flows in a space between the pipes, the steam generators (5) are arranged in separate boxes (6) and communicate with the reactor cavity (1) by means of circulation conduits for raising (8) and discharging (9) the lead coolant (10), the steam generators (5) and most of the circulation conduits (8) and (9) are arranged higher than the level of the lead coolant (10) within the reactor cavity (1), and the circulation pumps (7) are arranged within the reactor cavity (1) on the circulation conduits (8) and (9) for raising the "hot" lead coolant, and a technical means (13) is provided for ensuring intrinsic circulation of the lead coolant (10) through the active zone (4) when the circulation pumps (7) are switched off.
    • 本发明涉及核技术,并且旨在用于具有由主要为熔融铅或其合金形式的液态金属冷却剂冷却的快速反应堆的发电系统中。 本发明解决的问题在于减少反应器的每单位功率的铅冷却剂的比容量并且增加反应器的安全性。 该系统包括具有上盖(2)的反应器腔(1),布置在具有活性区(4)的空腔(1)反应器内的蒸汽发生器(5),循环泵(7),循环管道 )和(9)中,用于启动,操作和关闭反应器系统的致动机构系统和装置,其中蒸汽发生器(5)为管式热交换器的形式,其中引导冷却剂(10)在管道 ,当水蒸汽流入管道之间的空间时,蒸汽发生器(5)被布置在分开的箱子(6)中并且借助于循环管道与反应器腔室(1)连通,用于升高(8)和排出( 9)引导冷却剂(10),蒸汽发生器(5)和大部分循环管道(8)和(9)布置成高于反应器腔体(1)内的引导冷却剂(10)的液位,并且 循环泵(7)布置在循环导管(8)和(9)上的反应腔(1)内,用于提高“ 热“引导冷却剂,并且提供技术手段(13)用于当循环泵(7)关闭时确保引导冷却剂(10)通过活性区(4)的内在循环。
    • 2. 发明公开
    • ACTIVE ZONE OF A LEAD-COOLED FAST REACTOR
    • AKTIVER BEREICH EINES BLEIGEKLHLTEN SCHNELLEN REAKTORS
    • EP3101657A4
    • 2017-08-30
    • EP14881368
    • 2014-11-27
    • STATE ATOMIC ENERGY CORP ROSATOM ON BEHALF OF THE RUSSIAN FEDERATION
    • LEONOV VIKTOR NIKOLAEVICHLOPATKIN ALEKSANDR VIKTOROVICHRODINA ELENA ALEKSANDROVNACHERNOBROVKIN YURIY VASILIEVICH
    • G21C1/02G21C3/04G21C3/42G21C3/58G21C5/14
    • G21C3/04G21C1/02G21C1/022G21C3/42G21C3/58G21C5/14G21C2003/045G21Y2002/50G21Y2004/10G21Y2004/30Y02E30/34Y02E30/35Y02E30/38
    • An active zone of a reactor, a fuel element and a fuel assembly for creating said active zone are intended for use in fast reactors with a nitride fuel and a liquid-metal coolant primarily in the form of molten lead and alloys thereof. The problem addressed by the invention consists in creating an active zone with a void reactivity effect and with effective power flattening along the radius of the active zone. The active zone comprises a homogeneous uranium-plutonium nitride fuel, the mass fraction of which in the active zone is a minimum 0.305, and consists of 3 parts - a central part, an intermediate part and a peripheral part which form fuel assemblies comprising fuel elements with geometrically identical shells but with a differing height of the fuel column in the central part, the intermediate part and the peripheral part of the active zone, wherein the radial distribution of the fuel across the volume of the active zone is characterized by a stepped shape in a longitudinal section. The radius of the central part of the active zone is from 0.4 to 0.5 of the effective radius of the active zone, while the height of the fuel column in the fuel elements of the fuel assemblies in the central part is from 0.5 to 0.8 of the height of the fuel column in the fuel elements arranged in the fuel assemblies in the peripheral part of the active zone. The heights of the fuel columns forming a stepped intermediate part (with at least one step) for diameters ranging from 0.5 to 0.85 of the effective diameter of the active zone are selected within the range from 0.55 to 0.9 of the height of the fuel column in fuel elements arranged in the fuel assemblies in the peripheral part of the active zone.
    • 用于产生所述活性区的反应器,燃料元件和燃料组件的活性区域旨在用于具有主要为熔融铅及其合金形式的氮化物燃料和液态金属冷却剂的快速反应器中。 本发明解决的问题在于创建具有空隙反应性效应的有效区域以及沿有效区域的半径的有效功率平坦化。 活性区包括均质的铀 - 氮化钚燃料,其活性区中的质量分数最小为0.305,并且由3部分组成 - 中央部分,中间部分和周边部分,其形成包括燃料元件 具有几何相同的壳体,但在活性区域的中心部分,中间部分和周边部分具有不同高度的燃料柱,其中燃料在活性区体积上的径向分布的特征在于阶梯形状 在纵向部分。 有效区域中心部分的半径为有效区域的有效半径的0.4至0.5,而中心部分中的燃料组件的燃料元件中的燃料柱的高度为0.5至0.8 布置在活性区域的周边部分中的燃料组件中的燃料元件中的燃料柱的高度。 对于活性区的有效直径的直径为0.5至0.85的直径范围内的形成阶梯状中间部分(具有至少一个台阶)的燃料柱的高度选择在燃料柱高度的0.55至0.9的范围内 燃料元件布置在活性区的周边部分中的燃料组件中。