2014
DOI: 10.1016/j.nucengdes.2014.09.033
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A feasibility study on the criticality control method using radioactive vitrified forms for spent fuel storage

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Cited by 5 publications
(1 citation statement)
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“…Several studies on spent nuclear fuel have been done. Issues of concern include design of improved disposal concepts (Ahlstrm, 1997;Kim et al, 2014;Lee et al, 2012, transportation Jiang andWang, 2016), alternative uses or technologies (Mohamed, 2014;Kim et al, 2013). SNF, previously dissolved in a nitric acid solution, is extracted by TriButyl Phosphate (TBP) in the PUREX (Plutonium URanium EXtraction) process.…”
Section: Introductionmentioning
confidence: 99%
“…Several studies on spent nuclear fuel have been done. Issues of concern include design of improved disposal concepts (Ahlstrm, 1997;Kim et al, 2014;Lee et al, 2012, transportation Jiang andWang, 2016), alternative uses or technologies (Mohamed, 2014;Kim et al, 2013). SNF, previously dissolved in a nitric acid solution, is extracted by TriButyl Phosphate (TBP) in the PUREX (Plutonium URanium EXtraction) process.…”
Section: Introductionmentioning
confidence: 99%