Cheol-Woon Kim

Mo Sci Corporation (United States)

Author Statistics

Papers

Citation

H-Index

i-10 index

Research Trends

Author Order

Document Type

Co-Authors

Richard K. Brow

Missouri University of Science and Technology

Delbert E. Day

Missouri University of Science and Technology

Chandra S. Ray

Missouri University of Science and Technology

Jen-Hsien Hsu

Missouri University of Science and Technology

Hanzheng Wang

Zhejiang Chinese Medical University

Jincheng Bai

National University of Mongolia

Hai Xiao

Tsinghua University

Delbert E. Day

Missouri University of Science and Technology

Xinwei Lan

Northeastern University

Lei Yuan

Second Military Medical University

Cooperative Institutions

Missouri University of Science and Technology

American Ceramic Society

The Graduate Center, CUNY

Mo Sci Corporation (United States)

V. G. Khlopin Radium Institute

Pacific Northwest National Laboratory

Catholic University of America

Savannah River National Laboratory

Clemson University

University of Missouri

Author Statistics

Papers

Citation

H-Index

i-10 index

Research Field

High-Temperature Viscous Sealing Glasses for Solid Oxide Fuel Cells

Cheol-Woon Kim Richard K. Brow

Source

Cite

Citations (0)

The performance of Inconel 693 electrodes for processing an iron phosphate glass melt containing 26wt.% of a simulated low activity waste

Journal of Nuclear Materials (2013)

Jen-Hsien Hsu Joseph William Newkirk Cheol-Woon Kim Richard K. Brow Mark E. Schlesinger

Inconel

Borosilicate glass

Vitrification

Iron phosphate

Phosphate glass

Savannah River Site

10.1016/j.jnucmat.2013.09.055

Cite

Citations (11)

IRON PHOSPHATE GLASSES: AN ALTERNATIVE FOR VITRIFYING CERTAIN NUCLEAR WASTES

Delbert E. Day Cheol-Woon Kim

The unusual properties and beneficial characteristics of iron phosphate glasses, as viewed from the standpoint of alternative glasses for vitrifying nuclear and hazardous wastes (which contain components that make them poorly suited for vitrification in borosilicate glass), have been investigated by the University of Missouri-Rolla with support from the Environmental Management Science Program (EMSP), DOE [DEFG07- 96ER45618]. During the past year, the corrosion resistance of Inconel 690 and 693 coupons submerged in an iron phosphate melt at 1050 C for up to 155 days has been investigated to determine whether iron phosphate glasses could be melted in a Joule Heated Melter (JHM) equipped with such electrodes in the same manner as now being used to melt borosilicate glass. Substituting iron phosphate glasses for borosilicate glasses could significantly reduce the time and cost for clean up due to the higher waste loading possible in iron phosphate glass. The iron phosphate melt, which contained 30 wt% of the Hanford Low Activity Waste (LAW), did not corrode the Inconel 690 to any greater extent than what has been reported for Inconel 690 electrodes in the borosilicate melt in the JHM at the Defense Waste Processing Facility. Furthermore, Inconel 693 appeared to be an even better candidate for use in iron phosphate melts since its corrosion rate (0.7 {micro}m/day) was only about one half that (1.3 {micro}m/day) of Inconel 690. In the past year, the results of the research on iron phosphate glasses have been described in nine technical papers and one report and have been presented at four international and national meetings.

Borosilicate glass

Vitrification

Inconel

Iron phosphate

Phosphate glass

Hanford Site

10.2172/839298

Cite

Citations (1)

Iron Phosphate Glass for Immobilization of Hanford LAW

Ceramic transactions /Ceramic transactions (2004)

Cheol-Woon Kim Dongmei Zhu Delbert E. Day Dong‐Sang Kim John D. Vienna

Hanford Site

Iron phosphate

Source

Cite

Citations (13)

Reactive Fusion Welding for Ultra-High Temperature Ceramic Composite Joining

Cheol-Woon Kim Derek S. King Gregory E. Hilmas William G. Fahrenholtz

Abstract : Plasma and pulsed plasma arc welding (PAW and PPAW) processes were used to fusion weld ZrB2 containing 20 vol% ZrC. Varying welding parameters resulted in changes in weld pool shape and size, and the size of ZrB2 grains within the fusion zone (FZ). For PAW processes that resulted in a keyhole fusion zone (full penetration), the arc to workpiece power transfer efficiency was estimated to be 24%. Power transfer efficiency was estimated to drop to 18% for non-keyhole welds. The power transfer efficiency was not estimated for PPAW processes, but keyhole formation was observed for PPAW FZs. ZrB2 grain lengths were observed to decrease between binary PAW FZs (1 mm in length), and binary PPAW FZs (0.8 mm in length), and an increasing aspect ratio for ZrB2 grains in PPAW welds (up to 40:1) compared to PAW ZrB2 grain aspect ratios (up to 25:1) revealed that growth of ZrB2 was hindered in PPAW FZs. Grain growth was also observed to decrease with decreasing arc power. A high arc power resulted in high growth rates of ZrB2 and a textured FZ, whereas lower arc power FZs did not exhibit texture. A high current plasma arc (222 A) was used to increase the temperature of the weld pool, such that ZrB2 growth would follow the arc thermal gradient. ZrB2 growth occurred in the basal plane, resulting in grains with a plate-like morphology, where grain thickness increased by ledge growth. ZrB2 grain sizes within the FZ were observed to affect the strength of weldments. PM flexure strengths were measured to be 660 MPa and strengths were observed to drop to 140 MPa for PAW weldments and 170 MPa for PPAW weldments. Diffusion of C into the melt pool was observed to hinder ZrB2 grain growth significantly (150 m maximum ZrB2 grain size). The decreased maximum grain size resulted in average flexure strength of 250 MPa for ZrB2-ZrC-C weldments.

Keyhole

Plasma arc welding

Source

Cite

Citations (0)

IRON PHOSPHATE GLASSES: AN ALTERNATIVE FOR VITRIFYING CERTAIN NUCLEAR WASTES

Delbert E. Day Chandra S. Ray Cheol-Woon Kim

The U.S. Department of Energy (DOE) Environmental Management Science Program (EMSP) has funded research on iron phosphate glasses at the University of Missouri-Rolla (UMR) for the period from September 15, 1996 to September 30, 2004 (DE-FG07-96ER45618). The final report for the initial period from September 15, 1996 to September 14, 2000 (project number 55110) has been submitted previously and can be found at www.osti.gov/em52/final{_}reports/55110.pdf. This final report mainly describes the research conducted during the period from September 15, 2000 to September 30, 2004 (project number 73976)

Iron phosphate

Vitrification

10.2172/839385

Cite

Citations (7)

An alkali-free barium borosilicate viscous sealing glass for solid oxide fuel cells

Journal of Power Sources (2014)

Jen-Hsien Hsu Cheol-Woon Kim Richard K. Brow Joe Szabo Ray Crouch

Borosilicate glass

Thermal shock

Oxidizing agent

10.1016/j.jpowsour.2014.07.088

Cite

Citations (26)

An Analysis of Tree Growth in the XLPE Interface

Journal of the Korean Institute of Electrical and Electronic Material Engineers (1998)

Cheol-Woon Kim Hyun-Bin Park Taesung Kim Joon-Ung Lee

This study aims at analyzing to treeing in the solid-solid interface which is insulation type of cable junction parts, the proceeding of tree-growth and electrical breakdown were research in the study. Interface was made artificially to detect how it influenced the insulating ability of the whole system, the specimen were XLPE generally used in cable. The interface conditions were divided into two parts. First condition being the one focused on the surface of interface, it was treated with sand paper (#80, #600, #1200). For the second condition, the pressure of interface was varied as the value of 1, 5, 10 []. Using above conditions, treeing and breakdown properties on tree-growth were respectively compared in details. As a result, breakdown time was shorter for the full range of supplied voltage in the case of interface existed in the joint than non-existed interface. In the case of existed interface, the interface which had high-interface pressure and painted with silicon insulating oil was the best in the aspect of breakdown characteristics.

Electrical treeing

Interface (matter)

Source

Cite

Citations (0)

Potential Incorporation of Transuranics into Uranium Phases

Cheol-Woon Kim David J. Wronkiewicz Edgar C. Buck

The UO{sub 2} in spent nuclear fuel is unstable under moist oxidizing conditions and will be altered to uranyl oxide hydrate phases. The transuranics released during the corrosion of spent fuel may also be incorporated into the structures of secondary U{sup 6+} phases. The incorporation of radionuclides into alteration products will affect their mobility. A series of precipitation tests were conducted at either 150 or 90 C for seven days to determine the potential incorporation of Ce{sup 4+} and Nd{sup 3+} (surrogates for Pu{sup 4+} and Am{sup 3+}, respectively) into uranium phases. Ianthinite ([U{sub 2}{sup 4+}(UO{sub 2}){sub 4}O{sub 6}(OH){sub 4}(H{sub 2}O){sub 4}](H{sub 2}O){sub 5}) was produced by dissolving uranium oxyacetate in a solution containing copper acetate monohydrate as a reductant. The leachant used in these tests were doped with either 2.1 ppm cerium or 399 ppm neodymium. Inductively coupled plasma-mass spectrometer (ICP-MS) analysis of the solid phase reaction products which were dissolved in a HNO{sub 3} solution indicates that about 306 ppm Ce (K{sub d} = 146) was incorporated into ianthinite, while neodymium contents were much higher, being approximately 24,800 ppm (K{sub d} = 62). Solid phase examinations using an analytical transmission electron microscope/electron energy-loss spectrometer (AEM/EELS) indicate a uniform distribution of Nd, while Ce contents were below detection. Becquerelite (Ca[(UO{sub 2}){sub 6}O{sub 4}(OH){sub 6}]{center_dot}8H{sub 2}O) was produced by dissolving uranium oxyacetate in a solution containing calcium acetate. The leachant in these tests was doped with either 2.1 ppm cerium or 277 ppm neodymium. ICP-MS results indicate that about 33 ppm Ce (K{sub d}=16) was incorporated into becquerelite, while neodymium contents were higher, being approximately 1,300 ppm (K{sub d}=5). Homogeneous distribution of Nd in the solid phase was noted during AEM/EELS examination, and Ce contents were also below detection.

Uranyl

Uranium dioxide

Source

Cite

Citations (0)

Incorporation of cerium and neodymium in uranyl phases

Journal of Nuclear Materials (2006)

Cheol-Woon Kim David J. Wronkiewicz Robert J. Finch Edgar C. Buck

Uranyl

Neodymium

Praseodymium

10.1016/j.jnucmat.2006.02.087

Cite

Citations (20)