Abstract:
An apparatus, system and method for storing high level radioactive waste. In one aspect, the invention is a specially designed ring-like structure for providing neutron and gamma radiation shielding for high level radioactive materials that produce residual heat. In one embodiment, the ring-like structure is designed to be stackable upon itself so as to form a stacked structure that completely surrounds an internal containment boundary. In another embodiment, the ring-like structure is designed to have voids with specially designed geometries for receiving neutron absorbing material. In another aspect, the invention is a spacer apparatus designed to be located within the containment boundary to support the fuel basket and/or to improve conductive heat removal through the containment boundary. In yet another aspect, the invention is a fuel basket comprising one or more flux traps that regulate production of neutron radiation and plates constructed of a metal matrix composite material.
Abstract:
The present invention relates to a method for inspecting a fuel assembly (F) of a nuclear reactor, whereby the present invention comprises a number of fuel rods and inspection of the longitudinal sides of the fuel assembly (F) is effected. The invention also relates to a device for inspecting a fuel assembly (F). A distinguishing feature of the method according to the present invention is that partial inspection of the lower end surface (G) of the fuel assembly (F) takes place during one stage of the inspection.
Abstract translation:公开了具有以下玻璃组成的辐射屏蔽玻璃:SiO 2:10-35%; PbO:55-80%; B 2 O 3:0-10%; 0≤n≤0.0%; SrO:0-10%; BaO:0-10%; Na 2 O:0-10%; 和K 2 O 0:0〜10质量%,并且在波长400nm的10mm厚玻璃上测定的总透光率为50%以上。 还公开了具有相似玻璃组成的辐射屏蔽玻璃,可用作用于PET检查的γ射线屏蔽玻璃。
Abstract:
A flexible, lightweight radiation absorbing sheet or shield includes heavy metal particles in one layer and mid- atomic number particles in another layer, the layer that will adjacent to the patient. The shield is particularly intended for protection of the wearer and others from radiation emanating from a therapeutic source positioned within the patient's body. With the disclosed multi-layer shield construction, backseat tered radiation off the heavy metal particle layer, affecting the patient's adjacent tissue, is minimized.
Abstract:
The invention relates to nuclear engineering and can be used for fuel clusters of nuclear reactors, for distancing and fixing fuel elements, in particular in the fuel clusters of PWR and BWR reactors. The inventive distance lattice comprises cells which are used for mounting the fuel elements or guide channels and are formed by perpendicular crossing plates. Bent blades for mixing a coolant are embodied on the plate edges at the output of said coolant. Each cell is provided with an insertable distancing element for fixing the fuel element. Said invention makes it possible to increase the turning rigidity of the cells and the stability thereof, to simultaneously reduce the size of the fixation of the fuel elements or the guiding channels in the cells and to decrease the hydraulic resistance of the lattice.
Abstract:
Изобретение относится к области радиационной физики, радиохимии и медицины. Сущность изобретения: способ изготовления средства защиты от ионизирующего излучения, которая содержит, по крайней мере, два слоя материала (1) и (2), каждый из которых изготавливают в виде матрицы с распределенным по ее объему поглотителем ионизирующего излучения от источника (4). При этом химический состав поглотителя слоя материала, обращенного к источнику вторичного излучения, выбирают из условия, что энергия связи «K»-oбoлoчки хотя бы одного электрона поглотителя в первом или последующем слое была ниже энергии фотонного излучения, подлежащего ослаблению каждым слоем материала на 0,026-26 КэВ. Заявленное изобретение направлено на повышение эффективности ослабления ионизирующего излучения и снижение массы защитного материала.
Abstract:
Изобретение относится к атомной технике и может быть использовано в конструкциях тепловыделяющих сборок ядерных реакторов для дистанционирования и фиксации тепловыделяющих элементов, особенно в тепловыделяющих сборках реакторов PWR и BWR. Дистанционирующая решетка содержит ячейки, предназначенные для установки тепловыделяющих элементов или направляющих каналов и образованные перпендикулярными пересекающимися пластинами. На краях пластин на выходе потока теплоносителя выполнены отогнутые лопатки, предназначенные для перемешивания теплоносителя. Каждая ячейка снабжена вставным дистанционирующим элементом, предназначенным для фиксации тепловыделяющего элемента. В результате повышается жесткость ячеек на поворот и их устойчивость при одновременном снижении величины фиксации тепловыделяющих элементов или направляющих каналов в ячейках, а также снижается гидравлическое сопротивление решетки.
Abstract:
A radio-pharmaceutical transport system includes a pig (100) and a disposable plastic insert (300). Together, the pig (100) and the disposable plastic insert (300) provide a mechanism for transporting a syringe (10) containing a dose of a radio-pharmaceutical composition. The pig (100) includes a tungsten cylinder (110) that defines an elongated cavity (113) therein that is substantially coaxial with the tungsten cylinder (110). The cavity (113) is of sufficient size to receive therein a syringe (10). The tungsten cylinder (110) has a thickness sufficient to shield users from a PET radio-pharmaceutical without requiring additional shielding. The disposable plastic insert (300) is disposed within the cavity (113) and includes an elongated plastic envelope (310).
Abstract:
The invention relates to a fuel element (4) for a pressurised water nuclear reactor. A plurality of fuel rods (10) extending in an axial direction are guided into a plurality of quadratic spacers (12) which are arranged at a distance from each other and are grid-shaped. The edge thereof is formed, respectively, by four edge web pieces (14a, b). At least one spacer (12) has at least two edge web pieces (14a, b) which are different from each other and which are used to produce a force (F) acting upon flowing cooling water (K) on the fuel element (4) on the plane of said spacer (12) in a transversal manner in relation to the axial direction. As a result, a systematic, predetermined deformation of a core (5), comprising said fuel elements, is produced and is taken into account in the configuration thereof .
Abstract:
The present invention relates to a control rod blade for a boiling water reactor. The control rod blade (2) comprises a plurality of channels (3), which are arranged to receive an absorber material (10), a free edge portion with a recess (8), which comprises outlets for said channels (3), and a cover element (5), which is arranged to be attached by means of at least one welding operation such that it seals at least a part of said recess (8). Furthermore, the control rod blade (2) comprises a profile element (4), which, before said welding operation of the cover element (5) is performed, is arranged to be applied against a bottom surface (6a) in the recess (8) in a position such that the profile element (4) covers the outlets of said channels (3).