Dynamic Analyse of the Dry Process Fuel Sodium-Coded Fast Reactor Cycle

• Jeong Chang-Joon;Roh Gyu Hong;Choi Hangbok
• • Proceedings of the Korean Radioactive Waste Society Conference
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  • 2004.11a
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  • pp.142-144
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  • 2004
• PDF

3-D Moderator Circulation Simulation of CANDU6 Nuclear Reactor Using CFX-4.3

• Yoon, C.;Rhee, B.W.;Min, B.J.
• • Proceedings of the Korean Nuclear Society Conference
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  • 2001.10a
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  • pp.116-116
  • /
  • 2001
• PDF

Seawater Desalination Using An Advanced Small Integral Reactor-SMART

• Hwang, Young-Dong;Chang, Moon-Hee;Lee, Man-Ki
• • Proceedings of the Korean Nuclear Society Conference
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  • 1999.05a
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  • pp.447-447
  • /
  • 1999
• PDF

A Proliferation-Resistant Lead-Cooled Reactor for Transmutation of TRU and LLFP

• Kim Y.;Kim S. J.;Song T. Y.
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.05a
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  • pp.64-64
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  • 2004
• PDF

Feasibility Study on Heterogeneous ThO2-DUPIC Fuel Recycling in a CANDU Reactor

• Park Chang Je;Choi Hangbok;Yang Myung Seung
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.05a
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  • pp.67-67
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  • 2004
• PDF

Power Pulse Characteristics Following a LOCA in a DUPIC Fuel CANDU-6 Reactor

• Jeong, Chang-Joon;Rhee, Bo-Wook;Choi, Hang-Bok
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.697-698
  • /
  • 2005
• PDF

Load Analysis for Hinge Joint in Control Element Drive Mechanism of Integral Reactor

• Kim, Ji-Ho;Choi, Suhn;Zee, Sung-Qunn
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.879-880
  • /
  • 2005
• PDF

Preliminary Sensitivity Study on Gas-Cooled Reactor for NHDD System Using MARS-GCR

• Lee, Seung-Wook;Jeong, Jae-Jun;Lee, Won-Jae
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.10a
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  • pp.23-24
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  • 2005
• PDF

Conceptual Thermal-Hydraulic Design and Analytical Assessment of Spent Fuel Storage Pool for the Integral Reactor

• Kim, Min-Hwan;Kim, Jong-In;Zee, Sung-Kyun
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.10a
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  • pp.556-557
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  • 2005
• PDF

Mechanical Design Features of the KALIMER-600 Sodium-Cooled Reactor

• Lee, Jae-Han;Park, Chang-Gyu;Kim, Jong-Bum
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.10a
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  • pp.63-64
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  • 2005
• PDF

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