HTGR FUEL DEVELOPMENT: USE OF UO$sub 3$ TO LOAD CATION EXCHANGE RESIN FOR MICROSPHERE PREPARATION.

Haas, P

doi:10.2172/4627113

Cited by 3 publications

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“…This, of course, releases uranyl ion during reaction, thereby simply generating more reactant. This approach has been demonstrated [9] and is a preferred method if U0 3 is readily available. Typically, it would be in the case of fresh fuel.…”

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confidence: 99%

The Preparation of HTGR Fissile Fuel Kernels by Uranium-Loading of Ion Exchange Resins

Notz

Shaffer

1978

Radiochimica Acta

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Resin loading ¡Ion exchange resin/ HTGR fissile fuel / Nuclear fuel kernels / Uranium loading /Weak-acid resinAbstract Fissile fuel for High-Temperature Gas-Cooled Reactors (HTGRs) is fabricated in the form of small spheres ~300 um in diameter, each containing ~ 70 Mg of highly enriched uranium; the preferred chemical composition is a mixture of oxide and carbide. This report describes a process for loading weakacid ion exchange resin beads with uranium, from which the desired product is then derived by thermal treatment. The resin loading process has a major advantage over alternative, traditional methods because the process steps are relatively simple. This derives primarily from the fact that the resin is commercially available in the form of spherical beads. This factor is of significant benefit under any circumstances but especially in the case of the remote fabrication required for the highly radioactive 2 33 U recycle fuel. The process is based on the exchange of uranyl ion with the acid form of a carboxylate resin. This type and form of resin was chosen because (a) it contains only C, H, and O and is therefore free of other cations and additional undesirable elements such as N, S, or P; (b) it is available with a high enough concentration of exchange sites to achieve the necessary uranium density in the product. This usage differs from the usual applications of ion exchange resins because full loading is required, and the loaded resin itself is the desired product. In order to drive the reaction to essential completion, it is necessary to use acid-deficient uranyl nitrate [i. e., a composition equivalent to UO2(NO 3 ) 1-s (OH) 0 5 ]. This solution composition can be achieved either by extraction of HNOj with an amine in an organic solvent or by reaction with U0 3 . Each of these methods has been demonstrated in both batch and continuous modes. For recycle fuel, where uranyl nitrate solution is the natural product of reprocessing, amine extraction is preferred. For smaller operations, batch loading is the simpler approach; however, for larger operations, a single Higgins-type pulsed column can load 100 kg U per day in a continuous mode.

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confidence: 99%

The Preparation of HTGR Fissile Fuel Kernels by Uranium-Loading of Ion Exchange Resins

Notz

Shaffer

1978

Radiochimica Acta

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“…26 Material flow in the scrap recovery system -Case 4 (FRESH FUEL FABRICATION PLANT) Ill Table 4. 27 Material flow in the production of recycle fuel particles -Case 4 (REFABRICATION PLANT) 112 Table 4. 28 Material flow in the production of recycle fuel rods and elements -Case 4 (REFABRICATION PLANT) 113 Table 4.…”

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confidence: 99%

“…26 Annual dose to individuals (resulting from the radionuclides released in airbome effluents during the operating lifetime of the model HTGR fuel refabrication plant) from the time of cessation of plant operation until significant decay of all radionuclides occurs 151 Table 7. 27 Annual dose to the population (resulting from radionuclides released in airbome effluents from the model HTGR fuel refabrication plant) from the time of cessation of plant operations until significant decay of all radionuclides occurs 152 Annual cost for reduction of annual population dose out to a radius of 55 miles from airborne effluents from the model HTGR refabrication plant 206 environment. The model plants are representative of current proposed commercial designs or are based on technology that is being developed to fabricate uranium, thorium, and graphite into fuel elements.…”

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confidence: 99%