摘要:
본 발명은 냉각수 용기의 외벽 냉각장치에 관한 것으로, 원자로 공동 구조물에 마련되어 중대사고의 발생시 냉각수를 상기 단열재와 상기 원자로 공동 구조물 사이 공간으로 공급하는 냉각수 공급관과, 상기 단열재의 바닥면에 마련되어 상기 중대사고의 발생시 개방되어 상기 냉각수 공급관을 통해 공급된 냉각수를 상기 원자로 용기와 상기 단열재의 사이 공간으로 공급하는 냉각수유입부와, 상기 단열재의 측면 상부측에 마련되어 상기 중대사고의 발생시 개방되어 상기 원자로 용기와 상기 단열재의 사이 공간에서 열교환된 냉각수를 상기 단열재와 상기 원자로 공동 구조물의 사이로 순환시키는 냉각수유출부를 포함한다. 이와 같은 구성의 본 발명은 원자로공동 구조물 및 단열재 내부의 수위가 상기 냉각수 유출부 높이 이상인 동안에는 원자로용기 외벽냉각 및 그에 따른 냉각수 가열에 의해 냉각수유입구, 단열재 내부 유로, 냉각수유출구, 원자로 공동 구조물 내부(단열재 외부)로의 자연순환이 형성되어, 외부 구동력 없이 원자로용기 외벽을 냉각하고 중대사고의 발생시에도 노심 용융물이 원자로 용기의 밖으로 유출되는 것을 방지할 수 있는 효과가 있다.
摘要:
A lock for securing the head of a fuelling machine, defuelling machine or inspection machine to the end fitting of a fuel channel of a nuclear reactor is a rod and piston lock which engages or disengages according to the differential between the pressure in the snout cavity and the pressure in the fuelling machine magazine. The lock is engaged when the snout cavity pressure and the fuelling machine pressure are substantially equalized. When the pressure in the snout cavity is reduced sufficiently below the level of the pressure in the fuelling machine, the lock is engaged. The lock remains engaged if there is a drop in reactor pressure during refuelling and during reactor shutdown conditions. Engagement of the lock prevents inadvertent unclamping of the fuelling machine from the fuel channel.
摘要:
The invention relates to a holding device (1) for fuel elements in a reactor, in particular in a boiling water reactor, and a method for overhauling such a holding device (1). To this effect, there is a core grid, which is dismounted from a core shroud (3) in order to overhaul the holding device (1) and is replaced by a new forged core grid (2). An adapter ring (4) is to be inserted between the new core grid (2) and the core shroud (3). The adapter ring (4) is intended to be connected to the core grid (2), without welding, for example by shrinking.
摘要:
A pressure vessel (1), in particular a safety vessel for a boiling water nuclear power station, is built of reinforced concrete and has a metallic sealing structure (3). The pressure vessel (1) consists of an inner cylinder (16) and of an outer cylinder (14) which encloses the inner cylinder (16). A ring-shaped gap (2) between the inner cylinder (16) and the outer cylinder (14) holds the condensation chamber (17) and a spillway (19). The pressure vessel (1) can withstand an inner pressure of up to 20 bars, for example.
摘要:
Reactor block as well as a nuclear equipment utilizing it and method for the installation of such an equipment. This equipment is caracterized by a reactor bloc (2) constituting a displaceable module comprising a sheath (7) and a base (8), by a housing (1) intended to receive the reactor bloc (2) and by a module (3) for the obturation of the housing (1) and forming for example a storage pool for used nuclear fuel. The equipment according to the invention can constitute a transportable nuclear heater in the form of an integral assembly or separate elements.
摘要:
A mobile reactor radiation shielding solution prevents activation of structural materials to reduce a radiation dosage risk to living organisms and accelerates timetables for transport. The shielding solution can include: in-vessel neutron shield, in-vessel shadow shield, transport shield, and module shadow shield. In-vessel neutron shield reduces and prevents the activation of the structural materials and significantly reduces the need for heavy shielding to shield against the gamma emissions from activated structural materials. In-vessel shadow shield provides neutron and gamma shielding between the reactor and a balance-of-plant (BOP) module and control system. In-vessel shadow shield is placed near the active nuclear core to minimize size of the shield while maximizing the protected arc to shield radiation workers while preparing the nuclear reactor for transport. Transport shield is used during transportation when living organisms come into proximity of the reactor. Module shadow shield shields reactor control components and BOP module during operation.
摘要:
Изобретение относится к строительной технике, а именно, к защитным железобетонным ограждениям атомных электростанций. Технический результат заявленного изобретения заключается в повышении безопасности АЭС, упрощении конструкции защитного железобетонного ограждения АЭС, сокращении физических объемов и времени сооружения АЭС. Технический результат достигается за счет применения внутри бетонного блока между продольными арматурными стержнями и тыльной стороной защитного железобетонного ограждения стального просечно-вытяжного листа, в котором выполнены ромбовидные ячейки, сформированные несущими наклонными ребрами, которые закреплены на концевых опорах защитного железобетонного ограждения посредством сварного соединения. Применение стального просечно-вытяжного листа с ромбовидными ячейками в составе защитного ограждения уменьшенной толщины позволяет исключить попадание кусков бетона внутрь помещений АЭС. Кроме того, ввиду отсутствия необходимости в увеличении толщины защитного ограждения, обеспечивается как упрощение конструкции, так и уменьшение времени сооружения АЭС.