Abstract:90 Sr released into seawater from nuclear bomb testing and nuclear facility accident sites requires long-term monitoring. However, measuring 90 Sr in seawater is still difficult and time-consuming. This study is aimed at improving the preconcentration method for successive purification using DGA Resin chromatography, which is applied to 90 Sr analysis in seawater. At natural pH, the oxalate coprecipitation technique effectively collected Sr (84% in Sr yield) from seawater without Mg or Na. For 90 Sr determinat… Show more
“…Similarly, Sr 2+ was precipitated in the presence of oxalic acid. 40 This effect resulted in the Sr loss of 15%. TeB contained four carbon atoms in its molecule and consumed more nitrate and H + in its oxidation than glycol.…”
Section: Resultsmentioning
confidence: 99%
“…Thus, residual Fe appeared in the leachate even though the leachate pH had increased to 2.7. Similarly, Sr 2+ was precipitated in the presence of oxalic acid . This effect resulted in the Sr loss of 15%.…”
Sr-bearing
sludge is a hazardous waste that is commonly generated
by nuclear power plants and mineral refining operations. In this work,
Sr-bearing sludge was simulated and then cleanly recycled into high-purity
strontianite with hematite nanoparticles as a byproduct via a novel
hematite precipitation route. The sludge contained 26.1% Fe, 3.5%
Sr, and Si impurities. After dissolution in 1.2 M nitric acid, the
sludge was treated hydrothermally with the addition of glycol to precipitate
Fe effectively. Without the addition of glycol, only 52% Fe was hydrothermally
precipitated in the form of hematite aggregates. With the addition
of glycol at the optimal M
glycol/M
nitrate molar ratio of 0.4, nearly 100% Fe was
removed in the form of hematite nanoparticles with an average diameter
of 50 nm, whereas over 98% of Sr was retained in the leachate. The
generated hematite was highly purified with an Fe2O3 content of 95.23%. Sr was present at a high concentration
of 3.9 g/L in the treated leachate and further precipitated in the
form of strontianite with a purity of 96.8% through Na2CO3 addition. Tertiary butanol (TeB) exhibited a similar
Fe removal rate as glycol even though its optimal M
TeB/M
nitrate molar ratio was
0.1, which was approximately one-fourth the optimal M
glycol/M
nitrate molar ratio.
Fe removal involved spontaneous Fe3+ hydrolysis under hydrothermal
conditions and was promoted by increasing the pH of the redox reaction
between nitrate and glycol and/or TeB. The method reported here successfully
enabled the resource recycling of Sr-bearing sludge to generate high-purity
strontianite and hematite products without producing any secondary
waste.
“…Similarly, Sr 2+ was precipitated in the presence of oxalic acid. 40 This effect resulted in the Sr loss of 15%. TeB contained four carbon atoms in its molecule and consumed more nitrate and H + in its oxidation than glycol.…”
Section: Resultsmentioning
confidence: 99%
“…Thus, residual Fe appeared in the leachate even though the leachate pH had increased to 2.7. Similarly, Sr 2+ was precipitated in the presence of oxalic acid . This effect resulted in the Sr loss of 15%.…”
Sr-bearing
sludge is a hazardous waste that is commonly generated
by nuclear power plants and mineral refining operations. In this work,
Sr-bearing sludge was simulated and then cleanly recycled into high-purity
strontianite with hematite nanoparticles as a byproduct via a novel
hematite precipitation route. The sludge contained 26.1% Fe, 3.5%
Sr, and Si impurities. After dissolution in 1.2 M nitric acid, the
sludge was treated hydrothermally with the addition of glycol to precipitate
Fe effectively. Without the addition of glycol, only 52% Fe was hydrothermally
precipitated in the form of hematite aggregates. With the addition
of glycol at the optimal M
glycol/M
nitrate molar ratio of 0.4, nearly 100% Fe was
removed in the form of hematite nanoparticles with an average diameter
of 50 nm, whereas over 98% of Sr was retained in the leachate. The
generated hematite was highly purified with an Fe2O3 content of 95.23%. Sr was present at a high concentration
of 3.9 g/L in the treated leachate and further precipitated in the
form of strontianite with a purity of 96.8% through Na2CO3 addition. Tertiary butanol (TeB) exhibited a similar
Fe removal rate as glycol even though its optimal M
TeB/M
nitrate molar ratio was
0.1, which was approximately one-fourth the optimal M
glycol/M
nitrate molar ratio.
Fe removal involved spontaneous Fe3+ hydrolysis under hydrothermal
conditions and was promoted by increasing the pH of the redox reaction
between nitrate and glycol and/or TeB. The method reported here successfully
enabled the resource recycling of Sr-bearing sludge to generate high-purity
strontianite and hematite products without producing any secondary
waste.
“…(IL, USA). Detailed chemical separation and beta counting procedures are described elsewhere [22,23]. Beta particles were counted by a low background 2π gas flow proportional counter (LB−4200, Canberra, NV, USA) during 120 min intervals for more than 20 h. Typical Sr and Y yields were 82 ± 9 % and 95 ± 5 %, respectively.…”
The March 2011 earthquake and tsunami resulted in significant damage to the Fukushima Daiichi Nuclear Power Plant (FDNPP) and the subsequent release of radionuclides into the ocean. Here, we investigated the spatial distribution of strontium-90 (90Sr) and cesium-134/cesium-137 (134, 137Cs) in surface seawater of the coastal region near the FDNPP. In the coastal region, 90Sr activity was high, from 0.89 to 29.13 mBq L−1, with detectable FDNPP site-derived 134Cs. This indicated that release of 90Sr from the power plant was ongoing even in May 2013, as was that of 134Cs and 137Cs. 90Sr activities measured at open ocean sites corresponded to background derived from atmospheric nuclear weapons testing fallout. The FDNPP site-derived 90Sr/137Cs activity ratios in seawater were much higher than those in the direct discharge event in March 2011, in river input, and in seabed sediment; those ratios showed large variability, ranging from 0.16 to 0.64 despite a short sampling period. This FDNPP site-derived 90Sr/137Cs activity ratio suggests that these radionuclides were mainly derived from stagnant water in the reactor and turbine buildings of the FDNPP, while a different source with a low 90Sr/137Cs ratio could contribute to and produce the temporal variability of the 90Sr/137Cs ratio in coastal water. We estimated the release rate of 90Sr from the power plant as 9.6 ± 6.1 GBq day−1 in May 2013 on the basis of the relationship between 90Sr and 137Cs activity (90Sr/137Cs = 0.66 ± 0.05) and 137Cs release rate.
“…Samples prior to 2016 were analyzed using the procedure outlined in Casacuberta et al (2013) via coprecipitation with iron hydroxides and purified using anion (Bio-Rad AGI-X8, 100− 200 mesh) and cation (Bio-Rad AG50W-X8, 100−200 mesh) ion-exchange columns. 27 Samples analyzed in 2016 and onward were analyzed via an adapted method from Tazoe et al (2016), 28 which reduced the presence of competing beta signals (refer to S1) by utilizing Eichrom DGA resin 1 mL cartridges. Postcolumn samples were filtered through a 25 mm QMA filter, dried, and fixed onto beta mounts that were counted for 90 Y on Risø beta detectors (Risø National Lab; Roskilde, Denmark).…”
The Fukushima Dai-ichi Nuclear Power Plants (FDNPPs) accident in 2011 led to an unprecedented release of radionuclides into the environment. Particularly important are 90 Sr and 137 Cs due to their known health detriments and long half-lives (T 1/2 ≈ 30 y) relative to ecological systems. These radionuclides can be combined with the longer-lived 129 I (T 1/2 = 15.7 My) to trace hydrologic, atmospheric, oceanic, and geochemical processes. This study seeks to evaluate 137 Cs, 90 Sr, and 129 I concentrations in seawater off the coast of Japan, reconcile the sources of contaminated waters, and assess the application of 137 Cs/ 90 Sr, 129 I/ 137 Cs, and 129 I/ 90 Sr as oceanic tracers. We present new data from October 2015 and November 2016 off the coast of Japan, with observed concentrations reaching up to 198 ± 4 Bq•m −3 for 137 Cs, 9.1 ± 0.7 Bq•m −3 for 90 Sr, and (114 ± 2) × 10 −5 Bq•m −3 for 129 I. The utilization of activity ratios suggests a variety of sources, including sporadic and independent releases of radiocontaminants. Though overall concentrations are decreasing, concentrations are still elevated compared to pre-accident levels. In addition, Japan's Environment Minister has suggested that stored water from the FDNPPs may be released into the environment and thus continued efforts to understand the fate and distribution of these radionuclides is warranted.
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