Zobrazeno 1 - 10
of 14
pro vyhledávání: '"T. A. Gens"'
Publikováno v:
Nuclear Science and Engineering. 20:13-22
Potential processing methods for graphite-matrix nuclear reactor fuels which contain coated particles and/or ceramics are discussed. Both nonaqueous and aqueous processing methods are being develop...
Autor:
R. E. Blanco, T. A. Gens
Publikováno v:
Nuclear Science and Engineering. 11:267-273
A Modified Zirflex process was developed in the laboratory for dissolution of 1–10 % uranium-zirconium alloy fuels clad in Zircaloy-2 to produce a nitrate solution from which uranium can be recover...
Autor:
T. A. Gens
Publikováno v:
Nuclear Science and Engineering. 9:488-494
Processes for dissolving U-Zr snd Nb-U-Zr alloy fuels in ammonium fluoride solutions (Modified Zirflex processes) are developed. A nonaqueous process (Zircex process), in which high-zirconium alloys are hydrochlorinated at about 600 deg C, offers the
Publikováno v:
Chemischer Informationsdienst. 8
Autor:
R. L. Jolley, T. A. Gens
A new Zircex flowsheet is proposed in which the nonvolatile products from hydrochlorination of uranium-zirconium alloys are chlorinated with carbon tetrachloride, thereby avoiding the loss of 1 to 6% of the uranium observed in engineering development
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b1ca2b14fdc0872c265d70523dc1446f
https://doi.org/10.2172/4000618
https://doi.org/10.2172/4000618
Autor:
T. A. Gens
Report issued by the Oak Ridge National Laboratory discussing thermodynamic calculations of nuclear fuels. As stated in the introduction, "the equations developed in this report could be used to calculate the capacity of chlorine for transporting plu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ff99fa516262ddc8f10fb69fd34c3702
https://doi.org/10.2172/4005321
https://doi.org/10.2172/4005321
Autor:
T. A. Gens, F. G. Baird
Modified Zirflex process flowsheets were developed for recovering uranium from the newer power reactor fuel alloys after discharge from the reactor. The STR (1% U97% Zr-2% Sn) and EBWR Core-1 (93.5% U-5% Zr-1.5% Nb clad in Zircaloy-2) fuels are used
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c3660e029fcfa42518ab7bac3796f5fa
https://doi.org/10.2172/4195173
https://doi.org/10.2172/4195173