Hydrogen Behaviour in the IRWST of APR1400

• Kim, Han-Chul;Suh, Nam-Duk;Park, Jae-Hong;Kim, Bong-Hyun;Cho, Song-Won;Lee, Byung-Chul
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 2004.10a
  • /
  • pp.377-378
  • /
  • 2004
• PDF

Sensitivity of a Linear Cross Section Model in 3-Dimensional Core Transient Calculations

• Yang, Chae-Yong;Jang, Chang-Sun;Kim, In-Goo;Kim, Hho-Jung
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 2004.10a
  • /
  • pp.143-144
  • /
  • 2004
• PDF

Analysis of SG Level Control System Stability after Power Uprating at Kori 3&4 and Ygn 1&2

• Yoon, Duk-Joo;Lee, Jae-Yong;Lee, Chang-Sup;Oh, Hyung-Suk
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 2004.10a
  • /
  • pp.553-554
  • /
  • 2004
• PDF

TRAC-M/F77 Code Assessment for the Direct Vessel Injection Test During LBLOCA Reflood Phase

• Shin, An-Dong;Bang, Young-Seok;Lee, Jae-Hun;Lee, Jong-In
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 2001.05a
  • /
  • pp.235.1-235
  • /
  • 2001
• PDF

Failure Behavior of Steam Generator Tubes Containing Two Parallel Through-Wall Axial Cracks

• Lee, Jin-Ho;Park, Youn-Won;Song, Myung-Ho;Lee, Taek-Jin
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 2001.05a
  • /
  • pp.494.1-494
  • /
  • 2001
• PDF

Fretting-Wear Characteristics of Steam Generator Tubes Contacting with Foreign Object

• Jo Jong Chull;Jhung Myung Jo;Kim Woong Sik;Kim Hho Jung
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 2003.05a
  • /
  • pp.248-248
  • /
  • 2003
• PDF

An Application of RELAP5/MOD3 to the Post-LOCA Long Term Cooling Performance Evaluation

• Bang, Young-Seok;Jung, Jae-Won;Seul, Kwang-Won;Kim, Hho-Jung
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 1998.10a
  • /
  • pp.163.2-163
  • /
  • 1998
• PDF

Thermal Stress Analysis for a Circular Piping Subjected to Internally Stratified Flow

• Jo, Jong-Chull;Park, Young-Hwan;Kim, Yun-Il;Shin, Won-Ky
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 1999.05a
  • /
  • pp.118-118
  • /
  • 1999
• PDF

Fluidelastic Instability and Fretting-Wear Characteristics of Steam Generator Helical Tubes Subjected to Single-Phase External Flow and Two-Phase Internal Flow

• Jo Jong Chull;Jhung Myung Jo;Kim Woong Sik;Kim Hho Jung
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 2004.05a
  • /
  • pp.323-323
  • /
  • 2004
• PDF

Thermal Mixing in Water Pool under Steam-Discharging Condition

• Bang, Young-S.;Shin, An-Dong;Kim, In-Goo;Woo, Sweng-Woong;Song, Chul-Hwa
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 2005.05a
  • /
  • pp.561-562
  • /
  • 2005
• PDF

---