Adsorption characteristics of carbon on ion exchange resin in nuclear power plant

1999 ◽  
Vol 240 (1) ◽  
pp. 137-140 ◽  
Author(s):  
Kwang-Pill Lee ◽  
Hyung-Gik Kim ◽  
Keung-Shik Park ◽  
Duck-Won Kang ◽  
Eun-Hee Kim
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Ion Exchange ◽  
Nuclear Power ◽  
Exchange Resin ◽  
Ion Exchange Resin ◽  
Adsorption Characteristics

Physicochemical Properties of Vitrified Forms for LILW Generated From Korean Nuclear Power Plant

2015 ◽  
Vol 1744 ◽  
pp. 211-216 ◽  
Author(s):  
Cheon-Woo Kim ◽  
Hyehyun Lee ◽  
In-Sun Jang ◽  
Hyun-Jun Jo ◽  
Hyun-Je Cho
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Physicochemical Properties ◽  
Nuclear Power ◽  
Ion Exchange Resin ◽  
Immersion Test ◽  
Borosilicate Glasses ◽  
Irradiation Test ◽  
Regulatory Guidelines ◽  
Ph Buffer

ABSTRACTSince 1994, the KHNP has developed a vitrification technology to treat the LILW generated from Korean nuclear power plant. To vitrify the LILW including combustible Dry Active Waste (DAW) and Ion Exchange Resin (IER) containing Zeolite, two borosilicate glasses are formulated. One of the formulated glass, DG2, is for the DAW vitrification solely and the other one, AG8W1, is for the blended wastes (DAW & IER) vitrification in a commercial vitrification facility in HanUl (former Ulchin) nuclear power plant. The physicochemical properties of the two glasses have been evaluated. To evaluate the processability of the glasses, the viscosities and electrical conductivities of the glass melts were measured in the laboratory within a temperature range between 950 and 1,350 degrees C, respectively. The liquidus temperatures of the glasses were evaluated using a gradient furnace for DG2 and data from heat treatment for AG8W1. The Mössbauer spectroscopy for AG8W1 was employed to evaluate the relations between the redox equilibria of iron. In addition, to verify the waste acceptance criteria for the final disposal of the vitrified forms, the compressive strengths of the vitrified forms were tested after an immersion test, a thermal cycling test, and an irradiation test. To verify the chemical durability of the glasses, several tests such as PCT, ISO, VHT, Soxhlet, MCC-1, and ANS16.1 were carried out. The PCT showed leach rates of B, Na, Li and Si were much less than those of the benchmark glass. The ISO test was performed at 90 degrees C for 1,022 days and Cumulative Fraction Leached of all elements in the glasses were analyzed. According to the VHT, the glasses had an outstanding chemical resistance under humid environment at 200 degrees C for 7 days. The Soxhlet leaching was performed on rectangular glass samples at 98 degrees C for 30 days. To analyze the forward dissolution rates of major glass elements, the MCC-1 was conducted at temperatures of 40, 70, and 90 degrees C for three weeks in pH buffer solutions ranging from pH 4 to 11. The processability of the glasses was in the desired ranges. And the product quality of the glasses met all regulatory guidelines. Using two glasses, the CCIM commissioning tests in the UVF were successfully performed and they showed good workability.

scholarly journals Development of a New Generation of Ion Exchange Resin for Nuclear and Fossil Power Plant

2008 ◽  
Vol 19 (1) ◽  
pp. 29-34
Author(s):  
Shintaro TSUZUKI ◽  
Hidemi TAGAWA ◽  
Futoshi YAMASHITA ◽  
Ryutaro OKAMOTO
Keyword(s):  
Power Plant ◽  
Ion Exchange ◽  
Exchange Resin ◽  
Ion Exchange Resin ◽  
New Generation ◽  
Fossil Power Plant

scholarly journals Simulation of Ion Exchange Resin with Finite Difference Methods

Processes ◽  
2019 ◽  
Vol 7 (10) ◽  
pp. 675
Author(s):  
Zhu ◽  
Liu ◽  
Peng ◽  
Luo ◽  
Yu
Keyword(s):  
Ion Exchange ◽  
Finite Difference ◽  
Nuclear Power ◽  
Exchange Resin ◽  
Finite Difference Methods ◽  
Ion Exchange Resin ◽  
Operational Cycle ◽  
Good Consistency ◽  
Difference Methods ◽  
Set Up

Ion exchange resin is used to remove potentially corrosive impurities from coolant in the first circuit of a nuclear power plant. After one operational cycle, the used and unused resin in the mixed bed is discarded as solid waste. The aim of this work is to create a mathematical model to predict the operational cycle time of the mixed bed resin for reducing unused resin discharge. A partial differential equation (PDE) was set up with the conservation of matter. A finite difference method was used to solve the PDE. Matlab was the programming and calculating tool used in this work. The data from solution were obtained at different time and space nodes. The model was then verified experimentally using different ions on exchange columns. Concentrations of K+, Mn2+, and Cl- were calculated to verify the validation of the model by comparing it with experimental data. The calculated values showed good consistency with the experimental value.

Sign in / Sign up

Export Citation Format

Share Document