http://rdf.ncbi.nlm.nih.gov/pubchem/patent/FR-2344931-A1

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classificationIPCInventive http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21C19-307
filingDate 1976-03-18-04:00^^<http://www.w3.org/2001/XMLSchema#date>
inventor http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_6980835024d9d3a07b978366b6222585
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_803403a84b8b5e7edd18583e79873515
publicationDate 1977-10-14-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationNumber FR-2344931-A1
titleOfInvention PROCESS FOR EXTRACTING THE GASEOUS FISSION PRODUCTS FROM THE FUEL SALT OF A NUCLEAR REACTOR WITH MELT FUEL SALT
abstract Gaseous fission prods. are extracted from the combustible of a molten combustible salt nuclear reactor. In such a reactor, the combustible, generally Pu fluoride or U fluoride or a mixt. of fluorides of U or Th, dissolved in fluorides of Li-7 and of Be, is used also as heat transfer fluid in a prim. circuit. The circuit includes the reactor core, a pump and an exchanger in which heat is transferred to another molten salt, which exchanges its heat in turn, in a steam generator. Fission reactions produce radioactive gases, e.g. tritium and Xe 135, which must be removed. According to the invention, a reduced press. is established in the upper prt of a chamber fitted in the primary circuit so as to be partly filled with the combustible salt. The reduced press. causes degassing of the combustible. The process is more effective than existing processes, in which the gases are usually extracted by contacting the combustible with helium in the body of the pump, and the helium is purged. In those processes, the extn. is therefore carried out at a point in the prim. circuit where the salt is at the max. press, and the solubility of the gas is greater.
isCitedBy http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-106548811-A
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Total number of triples: 22.