2015
DOI: 10.1007/s10967-015-4500-z
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Production and isolation of homologs of flerovium and element 115 at the Lawrence Livermore National Laboratory Center for Accelerator Mass Spectrometry

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Cited by 13 publications
(3 citation statements)
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“…The 235 U solution (Solution 1) was prepared by dissolving 355 mg of metallic HEU (93.2% 235 U) in 35.5 mL of 3 M HNO 3 . The 237 U in Solutions 2–6 was produced in-house at the Center for Accelerator Mass Spectrometry (CAMS) of Lawrence Livermore National Laboratory , after bombardment of three depleted uranium foils (198–218 mg/cm 2 ) with 15.0 MeV protons ( 238 U­(p,x) 237 U). Following irradiation, the 238 U foils were dissolved in hydrochloric and nitric acids, and purified from most of the fission product impurities using a LN resin (Eichrom) based chromatography separation method. , The fourth batch of 237 U for validation (Solutions 7–9) was provided by Idaho National Laboratory (INL) from irradiation of a depleted uranium target with a beam of bremsstrahlung photons at 26 MeV end point energy followed by radiochemical separation of the coproduced fission products .…”
Section: Materials and Methodsmentioning
confidence: 99%
“…The 235 U solution (Solution 1) was prepared by dissolving 355 mg of metallic HEU (93.2% 235 U) in 35.5 mL of 3 M HNO 3 . The 237 U in Solutions 2–6 was produced in-house at the Center for Accelerator Mass Spectrometry (CAMS) of Lawrence Livermore National Laboratory , after bombardment of three depleted uranium foils (198–218 mg/cm 2 ) with 15.0 MeV protons ( 238 U­(p,x) 237 U). Following irradiation, the 238 U foils were dissolved in hydrochloric and nitric acids, and purified from most of the fission product impurities using a LN resin (Eichrom) based chromatography separation method. , The fourth batch of 237 U for validation (Solutions 7–9) was provided by Idaho National Laboratory (INL) from irradiation of a depleted uranium target with a beam of bremsstrahlung photons at 26 MeV end point energy followed by radiochemical separation of the coproduced fission products .…”
Section: Materials and Methodsmentioning
confidence: 99%
“…The nat In foil (99.9 %, Goodfellow Inc.) was dissolved in 1 M HCl and the 113 Sn was separated by passing the solution through an AG 1 9 8 anion exchange column (removing In) and eluting 113 Sn with 3 M HNO 3 as in Refs. [23,24].…”
Section: Reagents and Materialsmentioning
confidence: 99%
“…It was established that the K d of both elements in different media on cation- and anion-exchange sorbents was either very low or very high, which did not enable quantitatively separating them from each other [ 18 , 19 , 20 , 21 , 22 , 23 ]. Using commercial extraction chromatographic sorbents TEVA and LN (based on Aliquat 336 and HDEHP, respectively), it was possible to recover carrier-free Hg from macro-amounts of Au; however, 10–20% of Au remained on the column [ 24 , 25 , 26 ]. Sorbents Pb resin, DGA, and TK200 (based on 18-crown-6 derivative, diglycolamide, and trioctylphosphine oxide, accordingly) also made it possible to recover carrier-free Hg, but after this, it was impossible to desorb Au [ 27 , 28 ].…”
Section: Introductionmentioning
confidence: 99%