Literature survey: methods for the removal of iodine species from off-gases and liquid waste streams of nuclear power and nuclear fuel reprocessing plants, with emphasis on solid sorbents

Holladay, D.W.

doi:10.2172/6394859

Cited by 33 publications

(25 citation statements)

References 2 publications

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“…Liquid scrubbing systems using caustic solution, nitric acid, or Mercurex solution have been considered for capturing iodine, but shortcomings exist. These systems are capable to remove iodine at high concentrations, but are less effective with dilute streams which could be as low as 0.1–0.5 ppm .…”

Section: Introductionmentioning

confidence: 99%

Adsorption of iodine on hydrogen‐reduced silver‐exchanged mordenite: Experiments and modeling

2016

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The adsorption process of iodine, a major volatile radionuclide in the off‐gas streams of spent nuclear fuel reprocessing, on hydrogen‐reduced silver‐exchanged mordenite (Ag0Z) was studied at the micro‐scale. The gas‐solid mass transfer and reaction involved in the adsorption process were investigated and evaluated with appropriate models. Optimal conditions for reducing the silver‐exchanged mordenite (AgZ) in a hydrogen stream were determined. Kinetic and equilibrium data of iodine adsorption on Ag0Z were obtained by performing single‐layer adsorption experiments with experimental systems of high precision at 373–473 K over various iodine concentrations. Results indicate approximately 91% to 97% of the iodine adsorption was through the silver‐iodine reaction. The effect of temperature on the iodine loading capacity of Ag0Z was discussed. The Shrinking Core model describes the data well, and the primary rate controlling mechanisms were macro‐pore diffusion and silver‐iodine reaction. © 2016 American Institute of Chemical Engineers AIChE J, 63: 1024–1035, 2017

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Section: Introductionmentioning

confidence: 99%

Adsorption of iodine on hydrogen‐reduced silver‐exchanged mordenite: Experiments and modeling

2016

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“…The mercury must then be separated from the iodine and the resulting precipitant is conditionioned for storage [21]. Holladay [22] and Jubin [23] reported on the Iodox process for the removal of iodine from off-gas using HNO 3 (hyperazeotropic) solution.…”

Section: Capture Of Radioactive Contaminants By Wet Processesmentioning

confidence: 99%

Capture of harmful radioactive contaminants from off-gas stream using porous solid sorbents for clean environment – A review

Nandanwar

Coldsnow

Utgikar

et al. 2016

Chemical Engineering Journal

272

150

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Nuclear energy production is growing rapidly worldwide to satisfy increasing energy demands. Reprocessing of used nuclear fuel (UNF) is expected to play an important role for sustainable development of nuclear energy by increasing the energy extracted from the fuel and reducing the generation of the high level waste (HLW). However, during the reprocessing of Used Nuclear Fuel (UNF) gaseous radioactive nuclides including iodine, krypton, xenon, carbon, and tritium are released into the atmosphere through off-gas streams.The volatile iodine ( 129 I), and krypton ( 85 Kr) gases have long lived-isotopes; which have adverse effects on the environment as well as human health. Consequently, the capture of these two target radionuclides (species) is essential for the enhanced growth of nuclear energy. In this review we discuss several techniques for capture of volatile contaminants iodine, krypton, and xenon, focusing upon adsorption using solid sorbents, which has shown promising results for more than 70 years. Commonly used and recently developed sorbents are summarized in this article along with a short review of the results. Metal-organicframeworks (MOFs), gaining favor in recent years as sorbents for the capture of off-gas contaminants are also discussed. Finally, some considerations of future trends and prospects for investigations of the capture of volatile radionuclides are presented.

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“…Because an adsorbent system has advantages over the caustic scrubbing system, [1,2] several types of adsorbents for iodine have been developed. The iodine released in a dissolution step of reprocessing can easily diffuse over the extraction and partitioning processes of reprocessing and, finally, to the environment.…”

Section: Applicability Of a Model Predictingmentioning

confidence: 99%

Applicability of a Model Predicting Iodine-129 Profile in a Silver Nitrate Silica-Gel Column for Dissolver Off-Gas Treatment of Fuel Reprocessing

Mineo

Gotoh

Iizuka

et al. 2003

Separation Science and Technology

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The applicability of a mathematical model predicting iodine-129 profile in a silver nitrate silica-gel (hereinafter referred to as Ag-S) column for radioactive iodine treatment was examined using actual off-gas from a dissolution step of a spent nuclear fuel reprocessing test rig, where PWR spent fuels with burnups up to 44,000 MWdt 21 were dissolved. The iodine-129 profile predicted by the model showed good agreement with the iodine profile obtained in the experiment. It was suggested that the model would be useful to predict iodine profiles in an Ag-S column operated at 423 K for the off-gas treatment of actual spent fuel dissolution. Also, the values of the parameters used in the prediction, i.e., the effective diffusion coefficient and the Langmuir coefficient, were supposed to be applicable within the volumetric NO 2 concentration range lower than 1%.

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Literature survey: methods for the removal of iodine species from off-gases and liquid waste streams of nuclear power and nuclear fuel reprocessing plants, with emphasis on solid sorbents

Cited by 33 publications

References 2 publications

Adsorption of iodine on hydrogen‐reduced silver‐exchanged mordenite: Experiments and modeling

Adsorption of iodine on hydrogen‐reduced silver‐exchanged mordenite: Experiments and modeling

Capture of harmful radioactive contaminants from off-gas stream using porous solid sorbents for clean environment – A review

Applicability of a Model Predicting Iodine-129 Profile in a Silver Nitrate Silica-Gel Column for Dissolver Off-Gas Treatment of Fuel Reprocessing

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