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| 1 |
Determination of Performance Indicator Thresholds Based on Typical PSA Results
Kang, Dae-Il;Kim, Kil-Yoo;Hwang, Mee-Jung;Sung, Key-Yong;
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Korean Nuclear Society
, v.36, no.6, pp.485-496,
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| 2 |
The Effect of an Aggressive Cool-Down Following A Refueling Outage Accident in which a Pressurizer Safety valve is Stuck Open
Lim, Ho- Gon;Park, Jin-Hee;Jang, Seung-Cheol;
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Korean Nuclear Society
, v.36, no.6, pp.497-511,
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| 3 |
Nonlinear Finite Element Analysis of Containment Vessel by Considering the Tension stiffening Effect
Lee, Hong-Pyo;Choun, Young-Sun;Seo, Jeong-Moon;Shin, Jae-Chul;
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Korean Nuclear Society
, v.36, no.6, pp.512-527,
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| 4 |
On-line Generation of Three-Dimensional Core Power Distribution Using Incore Detector Signals to Monitor Safety Limits
Jang, Jin-Wook;Lee, Ki-Bog;Na, Man-Gyun;Lee, Yoon-Joon;
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Korean Nuclear Society
, v.36, no.6, pp.528-539,
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| 5 |
Development of a Diagnostic Algorithm with Acoustic Emission Sensors and Neural networks for Check Valves
Seong, Seung-Hwan;Kim, Jung-Soo;Hur, Seop;Kim, Jung-Tak;Park, Won-Man;
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Korean Nuclear Society
, v.36, no.6, pp.540-548,
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| 6 |
Application of Electromagnetic Fields to Improve the Removal Rate of Radioactive Corrosion Products
Kong, Tae-Young;Lee, Kun-Jai;Song, Min-Chul;
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Korean Nuclear Society
, v.36, no.6, pp.549-558,
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| 7 |
3-D CFD Analysis of the CANDU-6 Moderator Circulation Under Nnormal Operating Conditions
Yoon, Churl;Rhee, Bo-Wook;Min, Byung-Joo;
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Korean Nuclear Society
, v.36, no.6, pp.559-570,
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| 8 |
A Coherent Methodology for the Evaluation of a Steam Explosion Load Using TEXAS-V
Song, Jin-Ho;Park, Ik-Kyu;Kim, Jong-Hwan;
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Korean Nuclear Society
, v.36, no.6, pp.571-581,
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