Výsledky vyhledávání - "J. H. Shaffer"

The Recovery of Protactinium and Uranium from Molten Fluoride Systems by Precipitation as Oxides

Autor: G. M. Watson, W. R. Grimes, M. J. Kelly, D. R. Cuneo, J. E. Strain, J. H. Shaffer

Publikováno v: Nuclear Science and Engineering. 18:177-181

In the conceptual two-region molten-salt breeder reactor, fissionable U/ sup 233/ is recovered from the blanket as the decay product of Pa/sup 233/. Since equilibrium concentrations of Pa would result in appreciable parasitic neutron absorptions, the

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::8d016498c77ab1aca12cbee3d7250f90
https://doi.org/10.13182/nse64-a18316

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Boron Trifluoride as a Soluble Poison in Molten Salt Reactor Fuels

Autor: W. R. Grimes, J. H. Shaffer, G. M. Watson

Publikováno v: Nuclear Science and Engineering. 12:337-340

Control of a molten sait reactor by adjustment of the concentration of a nuclear poison that can be readily added to and removed from the circulating fuel is studied. This chemical control can be used, if necessary, in addition to the negative temper

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::a78b6a767127b1e68e7bff9ec297a798
https://doi.org/10.13182/nse62-a28083

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Distribution of iron during full loading of amberlite IRC-72 resin with uranium from nitrate solutions at 30/sup 0/C

Autor: J. H. Shaffer, C. W. Greene

The integrity of resin-based fuel kernels used in the fabrication of fuel elements for a high-temperature gas-cooled reactor will depend, in part, on the concentration of iron incorporated in the resin particles during their loading with uranium. Con

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::206e1711f29265b9ce281009ba1490ef
https://doi.org/10.2172/6566314

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Distribution of thorium during full loading of carboxylic acid cation exchange resins with uranium from nitrate solutions at 30 and 40/sup 0/C

Autor: J. H. Shaffer, C. W. Greene

The recycle of /sup 233/U for the refabrication of fuel elements for a high-temperature gas-cooled reactor will require an assessment of chemical specifications for impurities in the uranyl nitrate product stream from the fuel reprocessing facility.

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::05c296b2ed4b9c0e1c2f4cd482648c39
https://doi.org/10.2172/6442310

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Reaction of uranyl nitrate solutions with carboxylic acid cation exchange resins at 30, 40, and 50/sup 0/C. [Amberlite IRC-72; Duolite C-464]

Autor: J. H. Shaffer, C. W. Greene

An investigation of the reaction of uranyl nitrate solution with Amberlite IRC-72 and with Duolite C-464 resin was conducted under equilibrium conditions for application to a high-temperature gas-cooled reactor fuel refabrication facility. Test serie

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::dfa9a6ba5afd4754dab4fcf11c477984
https://doi.org/10.2172/6418684

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Reaction of uranyl nitrate solutions with amberlite IRC-72 cation exchange resin at 30/sup 0/C: a kinetic investigation for the HTGR fuel recycle plant

Autor: R. B. Evans, W. E. Shockley, J. H. Shaffer

A kinetic investigation of the reaction of uranyl nitrate solution with Amberlite IRC-72 cation exchange resin was conducted at 30/sup 0/C under conditions similar to those anticipated for a High-Temperature Gas-Cooled Reactor fuel refabrication faci

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::8e9338f8a97ab65d2413bf18f85ece4d
https://doi.org/10.2172/5268040

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