Chan Bock Lee

ORCID: 0000-0002-1404-4296
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About
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Research Areas
  • Nuclear Materials and Properties
  • Nuclear reactor physics and engineering
  • Fusion materials and technologies
  • Nuclear and radioactivity studies
  • Thermodynamic and Structural Properties of Metals and Alloys
  • Nuclear Engineering Thermal-Hydraulics
  • High Temperature Alloys and Creep
  • Molten salt chemistry and electrochemical processes
  • Radioactive element chemistry and processing
  • Hydrogen embrittlement and corrosion behaviors in metals
  • Graphite, nuclear technology, radiation studies
  • Nuclear materials and radiation effects
  • High-Temperature Coating Behaviors
  • Microstructure and Mechanical Properties of Steels
  • Fuel Cells and Related Materials
  • Advanced materials and composites
  • Engineering Applied Research
  • Nuclear Physics and Applications
  • Metal and Thin Film Mechanics
  • Intermetallics and Advanced Alloy Properties
  • Powder Metallurgy Techniques and Materials
  • Aluminum Alloy Microstructure Properties
  • Metal Alloys Wear and Properties
  • Advanced Welding Techniques Analysis
  • Hydrogen Storage and Materials

Korea Atomic Energy Research Institute
2010-2023

Metal fuel is being developed for the prototype generation-IV sodium-cooled fast reactor (PGSFR) to be built by 2028. U–Zr a driver initial core of PGSFR, and U–transuranics (TRU)–Zr will gradually replace through its qualification in PGSFR. Based on vast worldwide experiences fuel, work focused design, fabrication components, verification tests. U–TRU–Zr uses TRU recovered pyroelectrochemical processing spent PWR (pressurized water reactor) fuels, which contains highly radioactive minor...

10.1016/j.net.2016.08.001 article EN cc-by-nc-nd Nuclear Engineering and Technology 2016-08-29

Korea imports about 97% of its energy resources due to a lack available resources. In this status, the role nuclear power in electricity generation is expected become more important future years. particular, fast reactor system one most promising types for generation, because it can utilize efficiently uranium and reduce radioactive waste. Acknowledging importance policy, long-term advanced SFR development plan was authorized by KAEC 2008 updated 2011 which will be carried out toward...

10.1155/2013/290362 article EN cc-by Science and Technology of Nuclear Installations 2013-01-01

The Kori Unit 1, a first nuclear power plant (NPP) in South Korea stopped operation permanently on June 18, 2017 after 40 years of operation. Before the main decommissioning activities begin, full-system chemical decontamination (FSCDO) primary systems is planned to secure safety workers and minimize quantity radioactive waste. In this study, inventory at time 1 was investigated. CRUDTRAN code used make predictions by using actual maintenance history design data 1. Regarding steam generator...

10.1016/j.anucene.2023.109860 article EN cc-by Annals of Nuclear Energy 2023-05-02

Techniques to fabricate thorium-uranium dioxide fuel [(Th,U)O2] have been developed, and the thermal conductivity of (Th,U)O2 pellets has measured. Mixtures thorium (ThO2) uranium (UO2) powders were successfully wet-milled, compacted, sintered at 1700°C pellets. The wet-milling process results in a density 96 98% theoretical uniform distribution pellet. laser flash method was used measure diffusivity ThO2 pellets, conductivities (Th0.655U0.345)O2 (Th0.355U0.645)O2 found be lower than that or...

10.13182/nt04-a3518 article EN Nuclear Technology 2004-07-01

A mechanistic and engineering fission gas release model (MEGA) for uranium dioxide (UO2) fuel was developed. It based upon the diffusional of gases from inside grain to boundary external surface by interconnection bubbles in boundary. The capability MEGA validated a comparison with data base sensitivity analyses parameters. found that correctly predicts broad range burnups up 98MWd/kgU. Especially, enhancement high-burnup fuel, reduction at high burnup increasing UO2 size were be predicted...

10.1080/18811248.2008.9711415 article EN Journal of Nuclear Science and Technology 2008-01-01

Candidate coating materials for re-usable metallic nuclear fuel crucibles, TaC, TiC, ZrC, ZrO2, and Y2O3, were plasma-sprayed onto a niobium substrate. The microstructure of the coatings thermal cycling behavior characterized, U-Zr melt interaction studies carried out. TaC Y2O3 layers had uniform thickness, high density with only few small closed pores showing good consolidation, while ZrO2 not well consolidated considerable amount porosity. Thermal tests showed that adhesion was relatively...

10.5516/net.07.2013.012 article EN cc-by-nc-nd Nuclear Engineering and Technology 2013-10-01
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