摘要:
Provided is a member for nuclear reactors capable of being stably used without swelling or creep deformation even if directly exposed to neutrons with no additional improvements in nuclear reactor operation conditions or devices. A member for nuclear reactors comprises a core section comprising an aggregate of graphite particulates and a covering layer comprising a dense body of ceramic covering the core section. Because graphite that is affected by neutron irradiation is used in a state of aggregation of particulates and is not mutually connected, the shape and dimensions of the member for nuclear reactors is not affected even if there is swelling, creep deformation, or the like. Moreover, this member for nuclear reactors has a covering layer comprising a dense body of ceramic covering the core section. Because the covering layer comprising the dense body is more durable than graphite with respect to neutron irradiation, the shape and dimensions of the member for nuclear reactors are unlikely to be affected.
摘要:
The present invention relates to a coated microfibrous web, a method for producing the same, use thereof as a covering of a radiation protection material and also a radiation protection device. The coated microfibrous web comprises: (i) a microfibrous web which is impregnated with a fluoropolymer; and (ii) a layer comprising polyurethane, which is present only on one side of the microfibrous web.
摘要:
The invention relates to a radiation shielding construction for beam-guiding devices (28) of a particle accelerator and/or irradiation sites on a particle accelerator, comprising: a load-bearing housing (23) having concrete walls as side walls (14, 16), ceilings (18) and/or floors (10), wherein the concrete walls form a first radiation shielding layer, a second radiation shielding layer (20) comprising a loose or compacted filler mass, particularly soil, at the outside of at least some of the concrete walls, wherein the filler mass is pervious to water to a certain degree so that radionuclides could be flushed from the filler mass, wherein the concrete walls and the second radiation shielding layer (20) comprising the loose or compacted filler mass form an at least double-layer radiation shielding arrangement, and a sealing film (24) for the second radiation shielding layer (20), wherein the sealing film (24) surrounds and delimits the second radiation shielding layer (20) comprising the loose or compacted filler mass on the outside of the second radiation shielding layer (20), wherein the loose or compacted filler mass of the second radiation shielding layer (20) is enclosed between the concrete walls and the sealing film (24) in a water-proof manner, thereby immobilizing the filler mass hydro-geologically.
摘要:
A screened chamber, the therapy chamber, for ion therapy with neutrons having energy up to GeV is disclosed. The above is provided with screening on all but one sides and has a labyrinthine access on the non-screened side. The labyrinthine access comprises two shieldings longitudinally offset in the radiation axis and extending from opposing sides into the chamber, each of which covers more than half the open width of the access. The shieldings are embodied to be suitable to induce a spallation process with the incident neutron and the neutrons produced can be moderated. According to the invention, the central shielding measure is a combination shielding, comprising metal and a hydrogen-containing layer. High energy neutrons, caused by the so-called spallation reactions are generated, which are weakened in the second and further layers.
摘要:
The invention relates to a lead-free radiation protection material in the energy field of an x-ray tube with a voltage of between 60 and 125 kV. Said lead-free radiation protection material has a layered structure with at least two layers having different shielding characteristics.
摘要:
A method of forming a neutron-absorbing tube or a section of such tube, and the resulting tube. An elongate, generally rectangular metal ingot having a hollow interior is formed with at least one elongate metal divider in the interior forming chambers. The chambers are filled with a uniformly dispersed mixture of finely divided boron and particles of a finely divided metal, the ingot is then soaked to an elevated temperature and hot rolled to form a thin, rigid neutron-absorbing sheet having opposite metal edge portions and an elongated metal spacer portion at each metal divider. The sheet is then longitudinally bent at each spacer portion. A tube is formed by welding one or more bent sheet along the side edge portions.