Pechiney Ugine Kuhlmann

Electricite De France - Service National

Le Carbone Lorraine

Uranium Pechiney Ugine Kuhlmann

Electricite De France (service National) Pechiney Ugine-kuhlmann

Jacques Marcel Blum

Edmond Ventre

Jacques Maire

Michel Grenon

A control rod having a center of thermal neutron absorbing material is provided specifically for use within the core of a nuclear reactor, extending through the central zone of maximum flux density. The center is formed of a plurality of portions, normally three, arranged end to end and defining joins therebetween. A central one of said portions extends continuously through the zone of maximum flux density with the joins located outward of this zone.

Control rod for a nuclear reactor

The moderator structure is placed within a core space limited by a bottom wall, a top wall and a lateral reflector and is constituted by a stack of prismatic or spherical nodules applied in mutual contact in the three dimensions which prevent relative displacements of the nodules and so arranged as to form a lattice of interstices through which the molten salt is circulated.

Method for positioning moderator structure for the core of a molten-salt

Moderator structure for the core of a molten salt reactor

In a molten-salt reactor, a common vessel contains the reactor core, a neutron-moderating mass pierced by passages for the circulation of the fuel salt, at least one primary heat exchanger which is located close to the reactor core and through which the hot fuel salt passes after discharge from the core, pumps for circulating the cold fuel salt from the heat exchangers back into the reactor core. The free spaces defined within the reactor vessel between the core, the heat exchangers and the pumps except for the passages in which the molten fuel salt is circulated are packed with material which is compatible with the fuel salt.

Molten fuel-salt reactor

The present invention relates to the field of fused-salt nuclear reactors and its object is the extraction of the gases produced in the course of operation of these reactors. The process according to the invention consists in placing into position a piece of material permeable for gases and impermeable for the used fused salts, for instance, a piece of graphite, in such a way that part of the surface of this piece is in contact with the circuit of the radioactive salts and another part connected to a gas suction device. The piece could also be scavenged in its mass by a flow of inert gas. Application is contemplated in reactors using a mixture of lithium fluoride, beryllium fluoride, and uranium and/or thorium fluoride.

Growing community of inventors

Levallois Perret, France

Jacques Marcel Blum