Abstract:
Cet assemblage de combustible (1) pour réacteur nucléaire à eau sous pression comprend des premiers crayons (15) de combustible nucléaire ayant une première teneur massique en gadolinium et des deuxièmes crayons de combustible nucléaire (17) ayant une deuxième teneur massique en gadolinium. La deuxième teneur est supérieure à la première teneur. La première teneur massique est strictement supérieure à 2%.
Abstract:
Die Erfindung betrifft ein Blei-Ersatzmaterial für Strahlenschutzzwecke, wobei das Blei-Ersatzmaterial 12-22 Gew. -% Matrixmaterial, 0-75 Gew. -% Sn oder Sn-Verbindungen, 0-73 Gew. -% W oder W-Verbindungen, 0-80 Gew. -% Bi oder Bi-Verbindungen umfasst und wobei höchstens einer der Bestandteile 0 Gew. -% beträgt, für Nenn-Gesamtbleigleichwerte von 0,25-2,00 mm. Ferner betrifft die Erfindung ein Blei-Ersatzmaterial, das zusätzlich eines oder mehrere der Elemente Er, Ho, Dy, Tb, Gd, Eu, Sm, La, Ce, Nd, Cs, Ba, I Ta, Hf, Lu, Yb, Tm, Th, U und/oder ihrer Verbindungen und/oder CsI umfasst.
Abstract:
The transmutation of radioactive material using a hybrid transmutation reactor is disclosed wherein a kinetic proton source is used to collisionally induce the transmutation of radioactive material with the generation of thermal neutrons as a byproduct. Additionally, a system and method for the production of Tritium utilizing the thermal neutrons generated in the transmutation process is further described. The present invention offers advantages and improvements over existing nuclear reactor technologies in that nuclear waste may be rendered inert, or otherwise at least partially deactivated and/or made less dangerous, with the substantially simultaneous production of energy and/or Tritium as a byproduct of the transmutation process.
Abstract:
The invention relates to a heat-power engineering and can be used for steam turbine devices of power stations which use a nuclear and organic fuels. The inventive device comprises a reactor (1), a boiler (2), a high-pressure superheater (8), a low-pressure superheater (10), a steam turbine (3) provided with a high-pressure cylinder (4) and a low-pressure cylinder (5), an electrical generator (6), a steam condensator (7), a system for regenerative heating of supplied water (12). The reactor (1) and the boiler (2) are connected to a system for regenerative heating of supplied water (12) by means of independent pipelines (15 and 13). Said pipelines are fitted with check and control valves (16 and 14). The reactor (1) and the boiler (2) are connected to the high-pressure superheater (8) by means of independent pipelines (17 and 18) which are fitted with check and control valves (22 and 21). The high-pressure superheater (8) and the low-pressure superheater (10) are provided with bypass pipelines (9 and 11) which are fitted with check and control valves (23 and 24).
Abstract:
A method for mitigating stress corrosion cracking of a structural member of an atomic reactor plant which comprises injecting a platinum compound, a rhodium compound and a palladium compound into the reactor water in a pressure vessel of an atomic reactor, in a manner such that palladium is present in the reactor water in a less mole number than those of platinum and rhodium. The injection of the above compounds is preferably carried out during the lowering of the temperature of the reactor water from 150 DEG C to 80 DEG C upon the shutdown of a BWR plant. The platinum, rhodium and palladium in the form of ions in the reactor water are deposited on the surface of a structural member of an atomic reactor plant, thereby to significantly reduce the ECP of the structural member.
Abstract:
The invention concerns a method which consists in moving the fuel assembly (4) in the vertical position (19) and from down upwards from its storage position in a stowage basket (1) inside a pool (3), through a suction box (12) arranged above the basket (1) whereof the height is less than the axial length of the fuel assembly (4). The pool water (22) is sucked up through an opening of the box (12) emerging into the pool (3), so as to cause it to circulate in the box (12) in contact with the fuel assembly (4), in a substantially vertical direction and from down upwards and the water which has circulated in contact with the fuel assembly is recuperated. The device comprises a base plate (11) run through by an opening passage for the fuel assembly (4) designed to be urged to rest on the top part of the basket (1) and whereon the box (12) is supported and the water sucking means (6, 17, 18) in a lower part of the box.
Abstract:
A radiation shield (100) is provided for use on patients undergoing radiotherapy treatment. The shield (100) is made of a suitable radiation absorbing material for preventing the transmission of high energy radiation to the patient's non-treatment areas. The device may further comprise an exterior surface layer for absorbing low energy photons. The shield (100) is sized and shaped to conform to a patient's anatomy and to provide the necessary amount of absorbing material closest to the beam edge while not interfering with the beam. The shield may further comprise an optional cavity located on the interior surface of the shield (100) which may be lined with a soft compressible material for conforming to a patient's unique anatomy. The shield may be further provided with dosimeters mounted on the exterior surface of the leading edge as well as on the interior surface of the shield (100). The dosimeters may be connected in a systematic manner with the linear accelerator such that the machine could be automatically switched off or warnings given if the patient is receiving too much radiation scatter dose.