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At least 235 records · Page 13

Integrating decontamination strategies into a waste estimation support tool for radiological incidents - 15284

In the planning and preparedness stages for a response to a radiological incident, it is important to include waste management considerations when developing the decontamination/demolition/cleanup approach because waste management can be a driver for time and cost. An individualized type of strategy based on the occupancy of affected buildings may be an effective approach. The U.S. Environmental Protection Agency's (EPA's) Waste Estimation Support Tool (WEST) is a novel application of the Federal Emergency Management Agency (FEMA) Hazus-MH software. WEST enables users to estimate the characteristics, amount, and residual radioactivity of waste generated from remediation and cleanup activities after a radiological incident, including incidents caused by radiological dispersal devices and improvised nuclear devices, as well as nuclear power plant accidents. This paper will describe the recently released update to WEST, which includes the ability to export the waste estimate results back into ArcGIS for further visualization. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Electrorefining of Zircaloy-4 in LiCl-KCl to Decontaminate Irradiated Cladding - 16238

Electrorefining on unirradiated Zircaloy-4 specimen in LiCl-KCl was performed by managing the anode potential to identify whether high purity zirconium can be recovered in metallic form by electrorefining. Four different concentrations of ZrCl{sub 4} (0.1, 0.5, 1.0 and 2.0 wt%) were tested. Results indicate that high purity metallic zirconium was recovered at low concentration of ZrCl{sub 4} but ZrCl could be recovered at high concentration. The electrorefining experiments were simulated by a three-dimensional computational electrorefining model. Several physical properties were tested, and a set of physical properties was determined in the condition where chemical forms of cathode deposits estimated by the computational model accorded with the experimental results. Using those properties, co-deposition of zirconium and uranium was simulated in the geometry of a preliminary designed electro-refiner for irradiated Zircaloy claddings. Operating conditions that can lead to the formation of zirconium metal without ZrCl and uranium were calculated. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Concoction and Appraisal of Radiation Hardened Polyurethane Foams for DOE Decontamination and Decommissioning (D and D) Operations

Since World War 2, a number of nuclear facilities have been relocating their nuclear waste to long term storage, or final disposition. These facilities face monumental challenges in cleaning up the fixated transferrable radioactive waste that is left in these facilities after initial cleaning operations have ended. SRNL has identified a solution that is utilizing two-part epoxy foams with heavy metal additives for fixating and shielding transferable radioactive material that has accumulated in non uniform volumes. The purpose of this experiment is to make a library of data of physical characteristics of each foam and additive combination that will have data concerning how the material cures and performs in different environments with varying temperatures and how it will act and perform after being irradiated. Materials Being Tested: - Foam iT 7FR, Foam iT 23FR, 3M Fire Barrier foam, and Hilti CP620 foam; - Additives Bi, Bi2O{sub 3}, Na{sub 2}WO{sub 3}, and WO{sub 3} at 12.5% and 25%. What's being investigated: - Expansion data from each foam; - Radiation shielding data for each foam combination; - Peak temperatures for each foam. Utilized a FLIR thermal camera to find peak temperature and time it took the foam to reach it. No noticeable difference in volume or weight after blank foam samples sat in the environmental chamber for 24 hours except the 3M foam at the extreme relative humidity of 90% highlighted above. The more additives used in the foam, the more they were able to shield. The foams begin to saturate around 100% wt% where more additive used will not increase the shielding capability of the foam. Similar thermal dispersion in blanks and in samples with Bi additive. Time taken to peak temperature is very similar between the two. Similar peak temperatures in blanks and in Bi samples. Hilti had slightly elevated temperatures. All foams maintained their physical properties post environmental chamber except the 3M foam. With the increased sponginess from the high relative humidity's, 3M may be disqualified for further testing if its mechanical properties also suffer. While curing all foams had their peak temperature occur between 40 deg. C and 70 deg. C except the Hilti which occurred above 90 deg. C with and without additive. With this information, no foams would be disqualified. After radiation shielding studies, it was found that IT 14 with Bismuth and Bismuth Oxide Additives provided the best shielding of Co-60 with over 9% attenuation.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Laser Cleaning for Decontamination of a Nuclear Facility - 20609

This paper describes laser cleaning of contaminated tools in a nuclear power facility in Chalk River, Ontario Canada and also the same for EnergySolutions facility in Memphis facility. For the Chalk River facility, other methods of cleaning which included dry ice blasting, disassemble and wipe clean and steam cleaning, generated secondary waste and were time consuming. Laser cleaning of the tools in facility did not create secondary waste, was more efficient and safer for the operator. The laser cleaning method was compared with other methods. For the EnergySolutions facility in Memphis, laser cleaning was compared with hands on cleaning and laser removal by applying them to a rail car, a metal plate and a metal skate. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Sorbmatech{sup R}Cs, an Innovative Highly Selective Cs Sorbent for Wastewater Decontamination - 20065

The treatment of radioactive wastewater from the operating nuclear industry (energy production, reprocessing of spent fuel, decommissioning of shut-down facilities, etc.) or in case of incidental or accidental situation (such as Fukushima Daichii NPP accident) is an important issue requiring constant improvement of the technologies and techniques used to prevent radioactive releases into the environment and/or to reduce the production of secondary waste. CEA, Orano and CTI are collaborating since 2014, with the support of the French government's program 'investments for the future', to develop Sorbmatech{sup R}Cs, an innovative and patented selective sorbent (Grandjean and Barre 2014) to deal with the removal of radioactive {sup 137}Cs, one of the most hazardous isotope to be managed in nuclear waste, highly efficient either in agitated reactor or in column process. Sorbmatech{sup R}Cs sorbent consists of mesoporous silica particles loaded with potassium-copper hexacyanoferrate nanoparticles (KCu-HCF). This peculiar structure enables much faster sorption kinetics compared to denser crystalline structures, such as Silicotitanate or Zeolite sorbents, whose drawback consists in hindering the diffusion process through the material, and whose larger sorbent particles slow down the ion exchange process. The equilibrium of Sorbmatech{sup R}Cs is reached in few minutes, even at high flow rates in a fixed-bed column process (up to 10 m.h{sup -1} Darcy velocity) with low drop pressure. Moreover, Sorbmatech{sup R}Cs can be used over a wide pH range from 2 to 10 and has a very high selectivity towards {sup 137}Cs even in brine solution (saline, mineral or sea water). This new sorbent also has a K{sub d} higher than 10{sup 5} mL.g{sup -1} depending on the salinity of the wastewater, enabling a highly efficient removal of Cs trace in radioactive wastewater compared to Cs selective sorbent such as Zeolites and Silicotitanates. Its radiological resistance enables the treatment of high, medium and low activity wastewater. The CEA-Orano-CTI/ALSYS partnership leads to the development of a simple and low-cost synthetic route, which demonstrated large-scale manufacturing of the product on a batch of 100 kg. Two products have been developed and are ready for short run market introduction so far with grain size well adapted either for column processes or agitated reactors.. Finally, the industrial implementation has been studied and largely benefits from the properties of the sorbent. Indeed, its high sorption kinetics enable high flow rates resulting in a decrease of operation times, unit sizes, and volumes of secondary waste produced. Moreover, Sorbmatech{sup R}Cs is designed to be combined into a full and integrated solution, ranging from preliminary optimization of operating conditions through numerical dimensioning model, industrial implementation and treatment of the wastewater (through cartridge or preconditioned columns systems developed thanks to Orano's extensive expertise), to long-term stabilization of generated waste (under progress). (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Study on the Strategy for Final Disposal and Reuse of Decontamination Wastes after the Fukushima Daiichi NPP Accident - 20426

After the Fukushima Daiichi NPP accident, a large area of East Japan was contaminated by radio-Cs. To discuss the final disposal of the contaminated wastes off-site and the required development of related technologies, it is important to understand the volume and radiation concentration of the wastes after various treatments. For a scientific investigation purpose, a research committee has been formed by the Society for the Remediation of Radioactive Contamination in the Environment, which is independent from the Ministry of Environment. This committee's work is focused on discussing various scenarios for the final disposal considering a mass balance evaluation of the entire process, economic evaluations, and stakeholder consultation for final consensus. The current discussions of this committee are herein reported. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Impacts of Ionizing Radiation on Sulfur Chloride Compounds for Advanced Fuel Cladding Decontamination Processes

Tripling the nation’s nuclear energy capacity is a critical component for significantly increasing energy production and reducing energy costs for American families and businesses. Achieving this vision requires fuel cycle technologies that maximize resource utilization while minimizing radioactive waste generation. Advanced sulfur chloride–based chlorination technologies are being developed to enable efficient recycling of fuel cladding materials, which account for a significant fraction of used nuclear fuel. However, the impacts of ionizing radiation on the longevity and performance of these sulfur chloride compounds are not well established. Here, we will explore the effects of gamma and electron-beam irradiation on the chemical composition of select sulfur chloride reagents, specifically sulfur monochloride (S2Cl2) and thionyl chloride (SOCl2), and the impacts of pre-irradiation on the chlorination yield/chemical dissolution of surrogate aluminum alloy 6061 (AA6061-T6) materials.

38 - RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCL↗

Fabrication of Engineered Silica-Functionalized-Polyanilines Nanocomposites for Water Decontamination of Cadmium and Lead

In this study, two novel functionalized silica nanocomposites were synthesized via covalent bonding with nanopolyaniline (NPANI) and crosslinked nanopolyaniline (CrossNPANI) to produce [NSi-NPANI] and [NSi-CrossNPANI], respectively. The two nanocomposites were portrayed by SEM, FT-IR, HR-TEM, BET-surface and TGA. The HR-TEM images of [NSi-NPANI] and [NSi-CrossNPANI] confirmed the particle size in the range 14.28–21.43 and 26.19–35.71 nm, respectively and these two nanocomposites were successfully applied to remove divalent cadmium and lead from solutions. As compared to nanosilica [NSi] sorbent, the maximum capacity values of the two nanocomposites for divalent cadmium and lead were identified to increase from 100–250 µmole g{sup −1} (pH 1.0) to 750–800 µmole g{sup −1} (pH 7.0) and from 400–1050 µmole g{sup −1} (pH 1.0) to 650–1350 µmole g{sup −1} (pH 6.0), at the optimum conditions. The adsorption data were compared using two and three parameter equations based on Langmuir, Freundlich, Temkin, Dubinin-Radushkevich, Redlish-Peterson and sips models. The kinetic study of [NSi-NPANI] and [NSi-CrossNPANI] revealed that the pseudo-second order kinetic was the best model to explain the kinetic data for cadmium(II) and lead(II). The free energy of sorption (ΔG{sup o}), enthalpy (ΔH{sup o}), and entropy (ΔS{sup o}) changes were calculated to portend the nature of adsorption. Adsorptive extraction of toxic lead and cadmium from tap water and wastewater was successfully accomplished with the range of percentage recovery values 98.5–100.0 and 91.9–93.0%, respectively.

77 NANOSCIENCE AND NANOTECHNOLOGY↗

A mechanistic study on Decontamination of Methyl Orange Dyes from Aqueous Phase by Mesoporous Pulp Waste and Polyaniline

The dispersion-corrected density functional theory (DFT-D3) is used to investigate the mechanism of mesoporous pulp waste (MPW) and polyaniline (PANI) adsorptive removal methyl orange (MO) dye from their aqueous solutions. The results are absolutely reliable because of the sufficiently accurate method although such big systems are studied. It is demonstrated that hydrogen bond and Van Der Waals interactions play a significant role in MO adsorption by MPW and PANI. For MO adsorption by MPW, hydrogen bond and Van Der Waals interactions are both weakened in S{sub 1} state. In contrast, hydrogen bond and Van Der Waals interactions between PANI and MO are both enhanced in S{sub 1} state. The thermodynamic parameters such as enthalpy and free energy change reveal that the MO adsorption by MPW and PANI are spontaneous and exothermic. The adsorption of MO on MPW is less favorable in S{sub 1} state and the adsorption of MO on PANI is more favorable in S{sub 1} state. Therefore, the photoexcitation should be controlled during the MO adsorption by MPW and applied for MO adsorption by PANI. - Highlights: • The hydrogen bond and Van Der Waals interactions play a significant role in MO adsorption by MPW and PANI. • The influence of photoexcitation on adsorption has been studied firstly in our work. • The adsorption of MO on MPW is less favorable in S{sub 1} state and the adsorption of MO on PANI is more favorable in S{sub 1} state. • The MO adsorption by MPW and PANI are spontaneous and exothermic.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

DeSelenator: A Se-Removal Process for Environmental Decontamination of Wastewaters from Coal-Burning Power Plants

Selenium may become a toxic contaminant of freshwater systems when released into the environment through industrial wastewaters from mining, coal-burning power plants, or oil refining. Efficient and cost-effective Se-removal technologies are therefore necessary to reduce Se concentrations in these wastewaters to below the regulatory discharge limits. In this study, we have demonstrated an effective process that removes Se, mostly as selenate anions, from wastewaters generated by coal-burning power plants. This process, dubbed DeSelenator, leverages the high concentration of sulfate relative to selenate in the wastewater and the propensity of these oxyanions to cocrystallize with benzene-bis-iminoguanidinium (BBIG) cations into extremely insoluble salts (on par with BaSO 4 ). The SO 4 2− /SeO 4 2− cocrystallization with BBIG removes over 90% of S and Se from the wastewater. Following removal of the precipitate by filtration, the filtrate is passed over an anion-exchange resin that further reduces selenium concentration to 5 ppb, the EPA’s regulatory limit for freshwater systems. Finally, the effluent is passed over an activated carbon column, which removes 99.8% of the residual BBIG ligand remaining after crystallization, allowing for the safe discharge of the treated water into the environment. The Se-removal process was first optimized in the lab at the bench scale and then tested in the field at the Tennessee Valley Authority’s Bull Run coal-burning power plant. A technoeconomic assessment found the cost of water treatment with DeSelenator is on par with that of the active biological method, which is currently considered a state-of-the-art Se-removal technology.

anions↗