Patent · US Expired

Process and apparatus for extraction of gases produced during operation of a fused-salt nuclear reactor

US3993542A · kind A · utility

8Cited by
2References
10Claims
0Family size

Assignees

Inventors

Key dates

Filing dateFeb 6, 1975
Grant dateNov 23, 1976
Priority date
Expiry dateFeb 6, 1995

Classification

  • Technology area (CPC Y)Emerging Cross-Sectional Technologies
  • CPC primaryY02E30/30
  • WIPO fieldEngines, pumps, turbines
  • WIPO sectorMechanical engineering

Abstract

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.

Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.