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163 results on '"Tsai, Tsuey-Lin"'

8. Comparison of modeling methods for the effective diffusivities of IO3−estimated in compacted bentonite using through-diffusion tests under aerobic conditions

Author

Tsai, Tsuey-Lin and Tsai, Shih-Chin

Abstract

Diffusion is the predominant mechanism governing the transport of 129I through geosphere. Consequently, the assessment of the experimental findings on two-compartment diffusion reservoirs of IO3−within compacted bentonite involved the application of three distinct diffusion models: CC–CC (constant concentration), CC–VC (variable concentration), and VC–VC. To ensure the reliability of the obtained diffusion coefficients, multiple laboratory tests were performed for internal comparison. The experimental results revealed that IO3−diffusion coefficients were ranging from 3.83 × 10−13to 1.91 × 10−11m2/s. These techniques using three mathematical models could be conducted to estimate the diffusion coefficients of non- or weakly-sorbing radionuclides on compacted bentonite for safety assessment of radioactive waste final disposal.

Published
2024
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43. Development of an Activity Transport Model and In Situ Measurements on Deposited Radionuclides in the Primary Coolant Pipelines of the Chinshan Nuclear Power Plant

Author

Shih, Yu-Hung, Wang, Mei-Ya, Tsai, Tsuey-Lin, and Yeh, Tsung-Kuang

Abstract

AbstractActivated corrosion products deposited on the surfaces of fuel rods and pipelines contribute the majority of the radiation level in the primary system piping of a light water reactor and would have a significant impact on the safety of maintenance personnel or those involved in future decommissioning work. A computer model for site-specific applications, by the name of ACP_BWR, was developed to predict the distribution of activated corrosion products in the primary coolant circuit of a boiling water reactor (BWR). The prediction results were in reasonably good agreement with the data taken by periodic and in situ measurements at three locations after permanent shutdown of the BWR. Our analyses indicated that the 60Co, 54Mn, 58Co, and 59Fe activities in the core bypass, upper plenum, and lower downcomer regions were higher than those at other regions of the Chinshan Unit 1 reactor. Accordingly, the dose rates resulting from the activated corrosion products deposited at regions close to either side of the core shroud were comparatively high, surpassing those induced by neutron activation at these regions.

Published
2023
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45. Intercomparison of determining diffusion coefficients of I− in compacted bentonite using various mathematical models of through-diffusion experiments in the laboratory.

Author

Tsai, Tsuey-Lin, Tsai, Shih-Chin, Chang, Der-Ming, and Cheng, Wen-Hsi

Subjects
*DIFFUSION coefficients, *RADIOACTIVE waste repositories, *BENTONITE, *DIFFUSION, *MATHEMATICAL models
Abstract

Diffusion is the dominant process involved in the transport of 129I through geological media; therefore, the evaluation of the experimental results on the diffusion of I− through compacted bentonite was performed by three diffusion models, CC-CC, CC-VC, and VC-VC. Multiple experiments were cross-checked to verify internal consistency and thereby obtain reliable diffusion parameters. The results showed that I− diffusion coefficients ranged from 1.15 × 10–12 to 4.67 × 10–12 m2/s, which were consistent with those of the literature. These techniques could potentially be performed to measure the diffusion coefficients of non-sorbing or weakly sorbing radionuclides onto compacted bentonite in radioactive waste repositories. [ABSTRACT FROM AUTHOR]

Published
2021
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48. Characterization of solid particles sampled from condensates in boiling water reactor

Author

Tsai Tsuey-Lin, Liang-Cheng Chen, Tung-Jen Wen, and Yu-Hung Shih

Subjects
Nuclear and High Energy Physics, Iron oxide, Thermodynamics, Electron microprobe, 010403 inorganic & nuclear chemistry, 01 natural sciences, 010305 fluids & plasmas, 0104 chemical sciences, Corrosion, Amorphous solid, chemistry.chemical_compound, Nuclear Energy and Engineering, Chemical engineering, chemistry, Boiling, 0103 physical sciences, Boiling water reactor, Particle size, Dissolution
Abstract

The growth, activation and deposition of corrosion products are the primary sources of radiation buildup on the surface of out-of-core piping in nuclear power plants. The buildup of radiation can have negative effects on the performance of the facility and cause harm to staff during maintenance outages for refueling. This paper reports on the crystalline and amorphous structures of corrosion products sampled in the boiling water reactors in nuclear power plants of Kuo-Sheng and identified using an acid dissolving technique. X-ray diffraction, scanning electron microprobe and inductively coupled plasma-atomic emission spectroscopy were used to analyze the samples. The results indicate that the quantity of amorphous iron oxide at inlet of the condensate demineralizer in Unit 2 is higher than that in Unit 1. The proportion of crystalline to amorphous corrosion products can affect the efficiency of removal. Thus, these results can be used to explain the difference in removal efficiency of condensate demineralizers in different units. Moreover, the iron oxide structures with various properties were observed in different operational periods. It is probable that the higher proportion of amorphous structures with a smaller particle size would reduce efficiency in the removal of condensate demineralization in Unit 2.

Published
2016
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