Abstract:
A process for removal of tritium from materials that are contaminated thereby envisages the use of a detritiation reactor RT, in which the reaction for the removal of tritium from the waste takes place, said waste being recovered by means of a flow of moist inert gas in which an extremely low percentage of humidity is used. The heated waste releases a current of tritiated gases, said current of gases being removed from the reactor via the moist inert gas, which conveys it into a membrane reactor RM for decontamination. The membrane reactor, in fact, is able to remove selectively the tritium present in the mixture of gases: there is thus the dual advantage of purifying the mixture of gases and of recovering the tritium contained therein.
Abstract:
The invention relates to a composition capable of trapping hydrogen, comprising: (a) at least one mineral compound of the following formula (I) MX(OH) in which: M is a divalent transition element; O represents an oxygen atom; X is an atom selected from S, Se, Te, Po; and H is a hydrogen atom; and (b) at least one nitrate salt of the following formula (II) ZNO 3 in which: Z is a monovalent cation. The invention also relates to the use of such compositions either in a powdery form for trapping gaseous hydrogen par direct interaction, or in the form of an additive in a confinement material for example for trapping hydrogen released by radiolysis in radioactive waste packages.
Abstract:
Verfahren zur kontinuierlichen Wiederaufbereitung von Abgas eines Fusionsreaktors (1) mit einer Brennkammer (2), umfassend folgende Verfahrensschritte : kontinuierliches Abziehen eines Abgasvolumenstroms eines Fusionsreaktors (1) mit einer Metallfolienpumpe (3), erzeugen eines Plasmas aus dem Abgasvolumenstrom in der Metallfolienpumpe (3), wobei das erzeugte Plasmas innerhalb der Metallfolienpumpe (3) in gasförmige Wasserstoff-Isotopologe und Restgas aufgetrennt wird. Zuführen der Wasserstoff-Isotopologe aus der Metallfolienpumpe (3) in die Brennstoffspeicheranlage (10), und Zuführen des gasförmigen. Restgases in eine Tritium-Wiederaufbereitungsanlage (9) wobei die Temperatur des Restgases durch die mindestens eine Dampfsperre (18) konditioniert wird und über die Brennstoffspeicheranlage (10) in die Brennkammer (2) rückgeführt wird.
Abstract:
La présente invention se rapporte à un composé piégeur d'hydrogène, à un procédé de fabrication de ce composé et à ses utilisations. Elle trouve des applications dans toutes les situations où de l'hydrogène se dégage et où il doit être piégé notamment pour des raisons de sécurité. Le composé piègeur d'hydrogène de la présente invention se caractérise en ce qu'il comprend au moins un sel métallique de formule MX(OH), dans laquelle M représente un élément de transition divalent, par exemple Co ou Ni ; O représente un atome d'oxygène ; X représente un atome du groupe 16 de la classification, sauf O, par exemple un atome de soufre ; et H représente un atome d'hydrogène. Le composé piègeur d'hydrogène de la présente invention est efficace pour piéger l'hydrogène tant au sein d'un matériau que libre.
Abstract:
Examples of advanced fuel cycles for fusion reactors are described. Examples include fuel cycles for use in field reverse configuration (FRC) plasma reactors. In some examples, reaction gases may be removed from a fusion reactor between pulses (e.g. plasmoid collisions). In some examples, a D-3He reaction is performed, with the 3He provided from decay of byproducts of previous reactions (e.g. tritium).
Abstract:
Metallic beryllium pebbles for nuclear fusion reactors, wherein the grain sizes are adjusted to range from 0.1 to 1.8 mm and the average grain size is adjusted to lie from 0.05 to 0.6 mm, making it possible to strikingly increase tritium radioactivity. This makes it possible to enhance the efficiency for recovering tritium that serves as a fuel for nuclear fusion reactors while effectively suppressing the occurrence of swelling. Thus, it is allowed to advantageously avoid a reduction in the resistance against the external stress and in the heat conductivity of the metallic beryllium pebbles used as a material of the nuclear fusion reactors.
Abstract:
A system and method for producing tritium are disclosed. The system includes at least one neutron generator configured to generate neutrons. The system further includes at least one target comprising a lithium- containing material. The at least one target is configured to be irradiated by at least some of the neutrons and to produce tritium. The system further includes at least one collection structure configured to receive at least some of the tritium from the at least one target. The at least one collection structure comprises at least one gas conduit having an input configured to receive a carrier gas and an output configured to allow the carrier gas and the received tritium to flow out of the at least one gas conduit after the carrier gas has flowed along the at least one target.
Abstract:
The invention relates to a detritiation device comprising i) a furnace (1) for melting tritiated waste, said furnace comprising a hearth for receiving tritiated waste and a bubbling device for introducing a hydrogenated bubbling gas into the hearth during the melting and treatment of the tritiated waste in the furnace (1), and ii) a catalytic reactor with a quadrupole membrane (2) for treating the gas resulting from the melting and treatment of the tritiated waste in the furnace (1), said reactor comprising a membrane (20) for separating two flows of gas, the membrane (20) being permeable to the hydrogen isotopes. The invention also relates to an associated detritiation method.