Abstract:
This invention pertains to a method and apparatus for transporting syringes containing radioactive material. The invention includes assembling a radiopharmaceutical pig (10) so that the chamber of the radiopharmaceutical pig (10) contains a syringe (14) in a sharps container housing (26). The radiopharmaceutical pig (10) is disassembled, whereupon the syringe (14) is removed, discharged, and then replaced in the sharps container housing (26). A cap (24) of the sharps container (12) is affixed to the housing (26) of the sharps container (12), thus enclosing the contaminated syringe (14) therein. The radiopharmaceutical pig (10) is assembled so that its chamber contains the sharps container (12) and the syringe (14). The radiopharmaceutical pig (10) is transported to a dispoal area, where it is disassembled and the sharps container (12) containing the syringe (14) is placed in a particular disposal container.
Abstract:
A depressurising system (1) for depressurising plants, operating with pressurised steam and including a steam head (16), by injection of cold water under gravity from a reservoir (2) located at a higher level than the pressurised plant and connected thereto by a delivery duct (24) which forms a syphon (24a, 24b, 24c) and which is connected to the narrow section (10) of an ejector (6) into which steam flows in the event of an incident, the steam being drawn from a condenser (7) located downstream of the ejector (6), causing a drop in pressure which draws cold water from the tank (2) through the syphon which is thus overcome, enabling cold water to be injected into the pressurised plant.
Abstract:
An advanced gray rod control assembly (GRCA) is for a nuclear reactor. The reactor has a plurality of fuel assemblies each including numerous elongated fuel rods supported in an organized array by substantially transverse support grids, and a plurality of guide thimbles disposed through the support grids and along the fuel rods. The GRCA includes a spider assembly structured to provide controlled insertion of gray rod assemblies within the thimbles of the fuel assembly, thereby controlling the rate of power produced by the reactor. Each gray rod assembly includes an elongated tubular member, a first end plug, a second end plug, a substantially pure silver neutron-absorber disposed within the tubular member, and a support tube surrounding the neutron-absorber within the tubular member to resist silver-swelling. Delta-power of the reactor is improved by minimizing the exposed surface area of the absorber and distributing it among all of the rods of the GRCA.
Abstract:
The invention provides at least two electrochemical sensors positioned in a nuclear reactor, wherein at least one of the at least two electrochemical sensors has a zirconium electrode, and the at least two electrochemical sensors produce voltages proportional to an electrochemical corrosion potential for a surface that each of the at least two electrochemical sensors are installed upon. The invention also provides an arrangement configured to accept the voltages produced by the at least two electrochemical sensors, wherein the arrangement is configured to determine an electrochemical corrosion potential of a zirconium fuel rod in the nuclear reactor based upon the voltages of the at least two electrochemical sensors.
Abstract:
The invention provides a method for the encapsulation of a nuclear material, which comprises treating the material with an encapsulant, which comprises a cementitious material, such as Portland Cement, and curing, said cementitious material. The method is particularly suitable for the treatment of nuclear fuel materials such as uranium metal, complete Magnox fuel elements, or fuel element debris, for which encapsulation treatments have never previously been known. Such materials may be treated by the method of the invention in order to obtain products which remains stable and monolithic for many hundreds of years, and the invention thereby offers a safe and convenient alternative means of handling other than nuclear fuel reprocessing.
Abstract:
L'invention concerne un matériau composite de blindage neutronique et de maintien de la sous-criticité comprenant une matrice à base de résine vinylester et une charge inorganique capable de ralentir et d'absorber les neutrons. La résine vinylester peut être une résine époxyméthacrylate et la charge inorganique peut comprendre un borate de zinc et un hydrate d'alumine ou de l'hydroxyde de magnésium.
Abstract:
An improved nuclear shielding material that is flexible so as to effectively fill voids in radiation containment structures. Under very high temperatures the material is designed to undergo pyrolysis and transform into a strong ceramic material. The material contains a number of components, the first of which is a polymeric elastomer matrix such as two part self-polymerizing system like RTF silicone rubber. Additional components include: a compound to shield gamma radiation like tungsten carbide powder, a neutron absorbing/gamma blocking compound such as boron carbide powder, a heat conducting material such as diamond powder, a high temperature resistant compond such as silicon dioxide powder, a second neutron absorbing compound which also imparts electrical conductivity, namely barium sulfate powder, and a hydrogen gas surpassing component which readily absorbs hydrogen such as sponge palladium.
Abstract:
A system for making a connection between the interior and exterior of a compartment, comprising a door opening through the compartment wall, a connector body which can engage with the wall, and having a connection port through it, and a removable cover on the connector body. The body is engaged with the door opening, and an inner door within the compartment engages and removes the cover. A preferred construction creates a single line of confidence seal. The system is particularly suited for sterile compartments.