Experimental Study on Melt Decontamination of Stainless Steel and Carbon Steel Using Induction Melting

Zhao, Peng; Chung, Wonsub; Lee, Min-Cheol; Ahn, Seokyoung

doi:10.3390/met11081218

Cited by 5 publications

(4 citation statements)

References 5 publications

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“…In addition, all curing methods satisfied the disposal criterion. Furthermore, even though the compressive strength of the SABFS using GGBFS as a substitute for OPC was inferior to that of OPC (30)(31)(32)(33)(34)(35)(36)(37)(38)(39)(40), it was estimated to be higher than 20 MPa in all the conditions, and particularly, it was measured about 35 MPa in the case of water curing. The compressive strength of the SABFS was relatively lower in the air-dry, atmospheric steam, and high-pressure and high-temperature curing methods and it was attributed to insufficient hydration reactions due to the evaporation of the water.…”

Section: Effect Of Curing Methods On the Compressive Strength Of Sabfsmentioning

confidence: 91%

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Evaluation of the Solidification of Radioactive Wastes Using Blast Furnace Slag as a Solidifying Agent

Jeon,

Lee,

Lee

et al. 2023

Materials

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The decommissioning process of nuclear power facilities renders hundreds of thousands of tons of various types of waste. Of these different waste types, the amount of concrete waste (CW) varies greatly depending on the type of facility, operating history, and regulation standards. From the previous decommissioning projects, CW was estimated to comprise 60–80 wt.% of the total weight of radioactive wastes. This represents a significant technical challenge to any decommissioning project. Furthermore, the disposal costs for the generated concrete wastes are a substantial part of the total budget for any decommissioning project. Thus, the development of technologies effective for the reduction and recycling of CW has become an urgent agenda globally. Blast furnace slag (BFS) is an industrial byproduct containing a sufficient amount (higher than 30%) of CaO and it can be used as a substitute for ordinary Portland cement (OPC). However, there have been few studies on the application of BFS for the treatment of radioactive waste from decommissioning processes. This study was conducted to evaluate the performance of the solidification agent using ground granulated BFS (SABFS) to pack radioactive wastes, such as the coarse aggregates of CW (CACW), waste soil (WS), and metal waste (MW). The analytical results indicated that the CaO content of the ground granulated BFS was 36.8% and it was confirmed that calcium silicate hydrate (CSH) could be activated as the precursor of the hydration reactions. In addition, the optimum water-to-binder ratio was determined to be 0.25 and Ca(OH)2 and CaSO4 were found to be the most effective alkaline and sulfate activators for improving the compressive strength of the SABFS. The maximum packing capacities of the SABFS were determined to be 9 and 13 wt.% for WC and WM, respectively, when the content of CW was fixed at 50 wt.%. The results of the leaching tests using SABFS containing radioactive wastes contaminated with Co, Cs, and Sr indicated that their leachability indices met the acceptance level for disposal. Consequently, the SABFS can be used as a solidifying agent for the safe disposal of radioactive waste.

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Section: Effect Of Curing Methods On the Compressive Strength Of Sabfsmentioning

confidence: 91%

“…The particle size of soil samples used as WS was smaller than 75 µm. In contrast, MW was simulated with a stainless-steel plate (SUS 304) because it is known to be a common waste generated from the decommissioning process [35]. It was cut into 5 × 5 × 1 mm pieces before the experiments.…”

Section: Methodsmentioning

confidence: 99%

Evaluation of the Solidification of Radioactive Wastes Using Blast Furnace Slag as a Solidifying Agent

Jeon,

Lee,

Lee

et al. 2023

Materials

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“…Soil samples having a particle size smaller than 75 µm were obtained from a site in the vicinity of the Wolsong Nuclear Power Plant, which is one of the operating nuclear power plants in Korea, and they were used to simulate the waste soil [25]. On the contrary, the metal waste belongs to the group of ordinary dismantlement waste, and stainless-steel plate (SUS 304), which is commonly used in the pipeline of nuclear power facilities, was used in the experiments to simulate the metal waste after it was cut into 5 × 5 × 1 mm pieces [25,30]. The maximum capacity of SRC to pack coarse aggregate, waste soil, and metal waste was determined when its compressive strength satisfied the acceptance level (3.44 MPa) required by the disposal sites [25].…”

Section: Methodsmentioning

confidence: 99%

Solidification of Radioactive Wastes Using Recycled Cement Originating from Decommissioned Nuclear-Energy Facilities

Jeon,

Lee,

Lee

et al. 2024

Applied Sciences

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Hundreds of thousands of tons of waste are generated from decommissioned nuclear- power facilities, and it has become a critical global issue to secure technology for reducing and recycling this waste. Concrete waste (CW) is estimated to comprise 60–80% of the total waste, and concrete-waste powder (CWP) includes enough inorganic substances used as effective materials for waste treatment. Accordingly, it can be used to produce recycled cement (RC). This study aimed to evaluate the performance of a solidification agent manufactured using recycled cement (SRC) for the safe packing of radioactive wastes, such as coarse aggregates of CW, waste soil, and metal wastes originating from decommissioned nuclear facilities. The experimental results indicated that the most relevant incineration temperature of CWP for RC was 700 °C. The optimum water-to-binder ratio was determined to be 0.4, and the most relevant substitution ratio of ground granulated blast furnace slag for CWP was determined to be 15%. In addition, calcium silicate hydrate is the most effective hydration product for improving the compressive strength of SRC. The maximum packing capacities of the SRC for coarse aggregates, waste soil, and metal waste, which were simulated as radioactive wastes, were determined to be 30, 5, and 7 wt%, respectively. The results of leaching tests using SRC containing radioactive wastes contaminated with Co, Cs, and Sr indicated that their leachability indices met the acceptance level for disposal. Consequently, the RC composed of CWP can be used as a solidifying agent to safely dispose of radioactive wastes, such as coarse aggregates, waste soil, and metal waste.

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“…Decontamination efficiency varies widely depending on the radioisotope present. Radionuclides remaining in the molten material are homogeneously dispersed and effectively immobilized [16].…”

Section: Physical Decontaminationmentioning

confidence: 99%

Decontamination applications in primary circuit equipment of nuclear power plants

ÇETİN>

Acır²

2022

International Journal of Energy Studies

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Due to the reactions taking place in the reactor, radioactive contamination occurs on and/or near the surfaces of the equipment used in nuclear power plants. Contamination is a radioactive pollution in the solid phase, which may exist in solution or be carried as a gas/vapor. It can be caused by a very small amount of radioactive material, and since every known element has at least one radioactive isotope, there are more than a hundred elements that can cause contamination. Removing of this contamination by physical and chemical methods is defined as decontamination. The main purpose of decontamination is reducing the activity level of contaminated equipment which may occur during operation or after decommissioning of nuclear power plants. By decontamination process, the radioactive contamination formed on the surfaces or in the depths close to the surface of the equipment is removed by chemical and physical methods. Within the scope of this study, decontamination applications in the literature were explained; regulatory perspective and legislative infrastructure issues for Turkey were discussed. Within the scope of this study, the decontamination applications in the literature were explained, the regulations of the Regulatory Bodies in other countries for decontamination were examined, and in this direction, the regulatory perspective for Turkey and the suggestions for the legislative infrastructure were discussed.

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Experimental Study on Melt Decontamination of Stainless Steel and Carbon Steel Using Induction Melting

Cited by 5 publications

References 5 publications

Evaluation of the Solidification of Radioactive Wastes Using Blast Furnace Slag as a Solidifying Agent

Evaluation of the Solidification of Radioactive Wastes Using Blast Furnace Slag as a Solidifying Agent

Solidification of Radioactive Wastes Using Recycled Cement Originating from Decommissioned Nuclear-Energy Facilities

Decontamination applications in primary circuit equipment of nuclear power plants

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