1979
DOI: 10.2172/5819865
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Processing of irradiated, enriched uranium fuels at the Savannah River Plant

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Cited by 23 publications
(46 citation statements)
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“…The solubility of boric acid (H 3 BO 3 ) in 10 M HNO 3 (at 25 C) is approximately 2.75 g/L; therefore, exceeding the H 3 BO 3 solubility limit is not an issue. [12] Higher KF concentrations can be considered for the dissolution, although corrosion control issues and the precipitation of B as KBF 4 must also be taken into account. The precipitation of B as KBF 4 [5] The study also showed that dissolution rate decreased with increasing temperature in 0.13 M HF but increased with increasing temperature at 0.01 M and 0.07 M HF.…”
Section: Dissolution Rate Measurementsmentioning
confidence: 99%
“…The solubility of boric acid (H 3 BO 3 ) in 10 M HNO 3 (at 25 C) is approximately 2.75 g/L; therefore, exceeding the H 3 BO 3 solubility limit is not an issue. [12] Higher KF concentrations can be considered for the dissolution, although corrosion control issues and the precipitation of B as KBF 4 must also be taken into account. The precipitation of B as KBF 4 [5] The study also showed that dissolution rate decreased with increasing temperature in 0.13 M HF but increased with increasing temperature at 0.01 M and 0.07 M HF.…”
Section: Dissolution Rate Measurementsmentioning
confidence: 99%
“…The Actinide Technology Section has proposed the use of an nitric acid (HNO 3 ) and potassium fluoride (KF) flowsheet for stripping palladium (Pd) from palladium-coated kieselguhr (Pd/K) and removing aluminum (Al) metal foam from the TCAP coils. The basis for the HNO 3 -KF flowsheet is drawn from many sources.…”
Section: Overviewmentioning
confidence: 99%
“…In the first step, Pd metal is stripped from the Pd/K substrate in the coils using 8M HNO 3 . The acid is continually circulated through the coil at or near ambient temperature.…”
Section: Overviewmentioning
confidence: 99%
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“…However, the small amounts of Np, Am, and Cm (minor actinides) produced during fuel irradiation are not recovered and are currently discarded with the fission products as high level waste. If desired, Np produced in used reactor fuels can be recovered by making slight modifications to the PUREX process to control the Np valence and extraction into the solvent [4,5] as was performed at the US DOE's Savannah River Site for the production of 238 Pu for heat source applications [6].…”
Section: Introductionmentioning
confidence: 99%