Ymkwon Publication List

YOUNG-MIN KWON Ph. D
605 Clara Avenue, Unit 707, Saint Louis, MO 63112
Email: youngmin.kwon7@gmail.com
Linked in: http://www.linkedin.com/pub/young-min-kwon/54/a62/339

List of Publication
Journal Papers:

1. K. S. Ha, H. Y. Jeong, C. H. Cho, Y. M. Kwon, Y. B. Lee, and D. Hahn,
“Simulation of the EBR-II Loss-of-Flow Tests Using The MARS Code,” Nuclear
Technology, Vol.169, p.134, 2010.
2. Y. B. Lee, H. Y. Jeong, C. H. Cho, Y. M. Kwon, K. S Ha, W. P. Chang, S. D. Suk,
and D. Hahn, “Development of a Two-Dimensional Thermohydraulic Hot Pool
Model and Its Effects on Reactivity Feedback during a UTOP in Liquid Metal
Reactors,” Nuclear Engineering and Technology, Vol.41, p.1053, 2009.
3. H. Y. Jeong, K. S. Ha, Y. M. Kwon, Y. B. Lee, and D. Hahn, “Analysis of Three
Different Types of Blockage in a Sodium Flow Path with the MATRS-LMR-FB
Code,” Annals of Nuclear Energy, Vol.36, p.583, 2009.
4. K. S. Ha, H. Y. Jeong, Y. M. Kwon, Y. B. Lee, and D. Hahn, “An Enhanced Code
for the Safety Analysis of Pool-type Sodium-Cooled Fast Reactor,” Nuclear
Technology, Vol.164, p.221, 2008.
5. H. Y. Jeong, K. S. Ha, Y. M. Kwon, Y. B. Lee, D. Hahn, J. E, Cahalan, and F. E.
Dunn, “Evaluation of the Conduction Shape Factor with a CFD Code for a
Liquid-Metal Heat Transfer in Heated Triangular Rod Bundles,” Nuclear
Engineering and Design, Vol.237, p.648, 2007.
6. H. Y. Jeong, K. S. Ha, Y. M. Kwon, Y. B. Lee, and D. Hahn “A Dominant
Geometrical Parameter Affecting the Turbulent Mixing Rate in Rod Bundles,”
International Journal of Heat and Mass Transfer, Vol. 50, p.908, 2007.
7. H. Y. Jeong, K. S. Ha, Y. M. Kwon, W. P. Chang, and Y. B. Lee, “A Correlation
for Single Phase Turbulent Mixing in Square Rod Arrays under Highly Turbulent
Conditions,” Nuclear Engineering and Technology, Vol.38, p.1, 2006.
8. H. Y. Jeong, K. S. Ha, W. P. Chang, Y. M. Kwon, Y. B. Lee, “Modeling of Flow
Blockage in a Liquid Metal-Cooled Reactor Subassembly with a Subchannel
Analysis Code,” Nuclear Technology, Vol.149, p.71, 2005.
9. K. S. Ha, H. Y. Jeong, W. P. Chang, Y. M. Kwon, and Y. B. Lee, “Wire-Wrap
Model for Subchannel Blockage Analysis,” Journal of the Korean Nuclear
Society, Vol.36, p.165, 2004.
10. Y. B. Lee, Y. M. Kwon, K. D. Kim, W. P. Chang, and D. Hahn “Development of
Two-Dimensional Model for the Thermohydraulic Analysis of Hot Pool in Liquid
Metal Reactors,” Annals of Nuclear Energy, Vol.29, p.21, 2002.
11. W. P. Chang, Y. M. Kwon, K. D. Kim, Y. B. Lee, and D. Hahn, “Model
Development for Analysis of the Korea Advanced Liquid Metal Reactor,”
Nuclear Engineering and Design, Vol.217, p.63, 2002.

12. Y. M. Kwon, Y. B. Lee, W. P. Chang, D. Hahn, and K. D. Kim, "Development of
a System Analysis Code, SSC-K, for Inherent Safety Evaluation of the Korea
Advanced Liquid Metal Reactor," Journal of the Korean Nuclear Society, Vol.33,
p.209, 2001.
13. Y. M. Kwon and S. H. Chang, “A Mechanistic Critical Heat Flux Model for
High-Subcooling, High-Mass-Flux, and Small-Tube-Diameter Conditions,”
Journal of the Korean Nuclear Society, Vol.32, p.17, 2000.
14. Y. M. Kwon and S. H. Chang, “A Procedure to Predict Subcooled-Water-Flow-
Boiling CHF in Uniformly Heated Tubes for High-Heat-Flux Applications,”
Nuclear Technology, Vol.160, p.310, 2000.
15. Y. M. Kwon and S. H. Chang, “A Mechanistic Critical Heat Flux Model for Wide
Range of Subcooled and Low Quality Flow Boiling,” Nuclear Engineering and
Design, Vol.188, p.27, 1999.
16. Y. M. Kwon and S. H. Chang, “An Improved Mechanistic Model to Predict
Critical Heat Flux in Subcooled and Low Quality Convective Boiling,” Journal of
the Korean Nuclear Society, Vol.31, p.236, 1999.
17. Y. M. Kwon, H. S. Lim, and J. H. Song, “Design Options of Safety
Depressurization System,” Nuclear Engineering and Design, Vol. 179, p.287,
1998.
18. Y. M. Kwon and J. H. Song, “Realistic Large Break Loss of Coolant Accident
Mass and Energy Release and Temperature Analyses,” Journal of the Korean
Nuclear Society, Vol.29, p.229, June 1997.
19. Y. M. Kwon and J. H. Song, “Feasibility of Long Term Feed and Bleed Operation
for Total Loss of Feedwater Event,” Journal of the Korean Nuclear Society,
Vol.28, p.257, July 1996.
20. Y. M. Kwon, J. H. Song, and T. S. Ro, “Comparative Simulation of Feed and
Bleed Operation during the Total Loss of Feedwater Event by RELAP5/MOD3
and CEFALSH-4AS/REM Computer Codes,” Nuclear Technology, Vol.112,
p.181, 1995.
21. Y. M. Kwon, J. H. Song, and T. S. Ro, “Analysis of Total Loss of Feedwater
Event for the Determination of Safety Depressurization Bleed Capacity,” Journal
of the Korean Nuclear Society, Vol.27, p.470, 1995.

Conference Papers:
(* Papers that participated as a co-author are not included in the list completely.)

1. Y. M. Kwon, K. L. Lee, K. S. Ha, H. Y. Jeong, and W. P. Chang, “Radial Core
Expansion Reactivity Model in Limited Free-Bowing Reactor Constraint
System,” Transactions of the KNS Spring Meeting, Taebaek, May 2011.
2. Y. M. Kwon, K. L. Lee, K. S. Ha, H. Y. Jeong, and W. P. Chang, “A Study on
Inherent Safety of the 1,200MWe Pool-type Metal-fueled Sodium-cooled Fast
Reactor,” Proceedings of NTHAS-7: The 7th Korea-Japan Symposium on Nuclear
Thermal-Hydraulics and Safety, Paper N7P0093, Chuncheon, Korea, November
14-17, 2010.

3. Y. M. Kwon, K. L. Lee, K. S. Ha, W. P. Chang, and H. Y. Jeong, “Preliminary
Acceptance Criteria for Safety Analysis of KALIMER-600 SFR,” Transactions of
the KNS Autumn Meeting, Jeju, October 2010.
4. Y. M. Kwon, C. H. Cho, C. K. Park, E. K. Kim, H. Song, S. J. Kim, and H. Y.
Jeong, “Comparative Evaluation of Passive Safety Characteristics of 600, 1200,
and 1800MWe Burner Reactors,” Proceedings of NUTHOS-8: The 8th
International Conference on Nuclear Reactor Thermal Hydraulics, Operation and
Safety, Shanghai, China, October 10-14, 2010.
5. Y. M. Kwon, K. S. Ha, H. Y. Jeong, and W. P. Chang, “Local Flow Blockage in a
Wire-Wrapped Pin Bundle Subassembly for Liquid-Sodium Cooled Nuclear Fast
Reactor,” Proceedings of the 6th National Congress on Fluid Engineering, Busan,
August 2010.
6. Y. M. Kwon, C. K. Park, C. H. Cho, H. Song, E. K. Kim, and S. J. Kim “Safety
Evaluation of Pre-Conceptual Designs of Advanced Burner Reactors,”
Transactions of the KNS Spring Meeting, Pyeongchang, May 2010.
7. Y. M. Kwon, K. L. Lee, K. S. Ha, H. Y. Jeong, and W. P. Chang “Passive Safety
Characteristics of the 1,200MWe GEN-IV Sodium-Cooled Fast Reactor,”
8. H. Y. Jeong, K. S. Ha, Y. M. Kwon, W. P. Chang, S. D. Suk, and K. L. Lee,
“Influence of Pool Modeling in the Analysis of Asymmetrical Test in Phenix
Reactor,” Transactions of the KNS Spring Meeting, Pyeongchang, May 2010.
9. K. S. Ha, Y. M. Kwon, W. P. Chang, K. L. Lee, and H. Y. Jeong “Long-term
Cooling Capability of KALIMER-600 Passive Decay Heat Removal System,”
10. W. P. Chang, Y. M. Kwon, K. S. Ha, and H. Y. Jeong “Analysis of Local
Recirculation Flow under Sub-channel Blockage Accident,” Transactions of the
KNS Spring Meeting, Pyeongchang, May 2010.
11. Y. M. Kwon, K. S. Ha, H. Y. Jeong, and W. P. Chang, “Thermal-hydraulic
Characteristics of Local Blockage within a Wire-Wrapped Pin Bundle
Subassembly for Sodium-cooled Fast Reactor,” Proceedings of the KSME
Autumn Meeting, pp.2650-2654, 2009.
12. R. Nakai, A. Vasile, J. E. Cahalan, and Y.M. Kwon, “Current Status and
Prospects of R&D on Generation IV SFR Safety and Operation Project,”
Proceedings of the GIF Symposium, Paris, France, September 2009.
13. Y. M. Kwon, C. K. Park, C. H. Cho, H. Song, E. K. Kim, and S. J. Kim, “Passive
Safety Features of KALIMER-600 Burner Reactor for Unprotected Undercooling
Events,” Transactions of the KNS Autumn Meeting, Gyeongju, October 2009.
14. Y. M. Kwon, H. Y. Jeong, K. S. Ha, and W. P. Chang, “Development of
Preliminary PIRTs of Thermal Hydraulic Phenomena for KALIMER-600,”
Transactions of the KNS Autumn Meeting, Gyeongju, October 2009.
15. Y. M. Kwon, H. Y. Jeong, K. S. Ha, H. Song, and S. J. Kim, “Assessment of the
KALIMER-600 Burner Reactor Responses to Unprotected Transient Overpower,”
Transactions of the KNS Spring Meeting, May 2009.
16. Y. M. Kwon, K. S. Ha, H. Y. Jeong, and W. P. Chang, “A Whole Core
Subassembly Treatment in the SSC-K Sodium-cooled Fast Reactor System

Analysis Code,” Proceedings of the 4th Korea-China Workshop on Nuclear
Reactor Thermal Hydraulics, Jeju, Korea, May, 2009.
17. Y. M. Kwon, H. Y. Jeong, C. H. Cho, K. S. Ha, and S. J. Kim, “Passive Safety
Design Characteristics of the KALIMER-600 Burner Reactor,” Proceedings of
ICAPP ’09: International Congress on Advances in Nuclear Power Plants, Paper
9206, Tokyo, Japan, May 10-14, 2009.
18. Y. M. Kwon, H. Y. Jeong, and K. S. Ha, “Impact of Multi-dimensional Core
Thermal-hydraulics on Inherent Safety of Sodium-cooled Fast Reactor,”
Proceedings of the KSME Autumn Meeting, pp.3175-3180, November 2008.
19. Y. M. Kwon, H. Y. Jeong, C. H. Cho, K. S. Ha, H. Song, and S. J. Kim,
“Evaluation of Passive Safety Design Features of the KALIMER-600 Burner
Reactor,” Proceedings of the 8th Korea-China Joint Workshop on Nuclear Waste
Management and Fast Reactor Technologies, Jeju, Korea, November 13-15, 2008.
20. Y. M. Kwon, K. S. Ha, H. Y. Jeong, C. H. Cho, and S. D. Suk, “Unprotected
Transient Overpower Accident in a Sodium-Cooled Fast Reactor Using a Three-
dimensional Core Thermal-hydraulic Calculation,” Transactions of the KNS
Autumn Meeting, Pyeongchang, October 2008.
21. Y. M. Kwon, K. S. Ha, H. Y. Jeong, W. P. Chang, Y. B. Lee, and D. Hahn,
“Inherent Safety Evaluation of Pool-type Liquid Metal Fast Reactor by a
Multidimensional Thermal-hydraulic Calculation,” Proceedings of ICAPP ’08:
International Congress on Advances in Nuclear Power Plants, Paper 8157,
Anaheim, CA, June 8-12, 2008.
22. Y. M. Kwon, H. Y. Jeong, and Y. B. Lee, “Evaluation of Thermal-hydraulic
Mixing Effect in Upper Plenum of Sodium-cooled Nuclear Reactors,”
Proceedings of the KSME Spring Meeting on Thermal and Energy, pp.364-367,
2008
23. Y. M. Kwon, H. Y. Jeong, C. H. Cho, S. D. Suk, and Y. B. Lee, “Calculation
Model of Radial Core Expansion Reactivity Feedback in Sodium-cooled Fast
Reactors,” Transactions of the KNS Spring Meeting, Gyeongju, May 2008.
24. Y. M. Kwon, H. Y. Jeong, W. P. Chang, and Y. B. Lee “Calculation of a Doppler
Reactivity Effect in the Metal-Fueled KALIMER Reactor,” Proceedings of the
KNS Autumn Meeting, October 2007.
25. Y. M. Kwon, H. Y. Jeong, K. S. Ha, W. P. Chang, Y. B. Lee, and D. Hahn,
“Scoping System Analysis of KALIMER-600 Design Concept,” Proceedings of
ICONE-14: The 14th International Conference on Nuclear Engineering, Paper
89514, Miami, FL, June 17-20, 2006.
26. Y. M. Kwon, W. P. Chang, Y. B. Lee, D. Hahn, and J. E. Cahalan, “Comparative
Analysis for Evaluating Passive Safety Design Features of the KALIMER-150,”
Trans. Ame. Nucl. Soc., San Diego, June 2005.
27. H. Y. Jeong, Y. M. Kwon, W. P. Chang, and Y. B. Lee, “Passive Safety of the
600MWe Korean Advanced Liquid Metal-Cooled Reactor,” Trans. Ame. Nucl.
Soc., San Diego, June 2005.
28. Y. M. Kwon, H. Y. Jeong, W. P. Chang, and Y. B. Lee, “Negative Buoyancy
Phenomenon in the LMFR Hot Pool during Scrammed Transients,” Proceedings
of the KNS Spring Meeting, Jeju, May 2005.

29. Y. M. Kwon, K. S. Ha, H. Y. Jeong, W. P. Chang, and Y. B. Lee, “Self-Power
Regulating Characteristics of the KALIMER-150 Core during Unscrammed
Accidents,” Proceedings of the KNS Spring Meeting, Jeju, May 2005.
30. Y. M. Kwon, H. Y. Jeong, K. S. Ha, W. P. Chang, Y. B. Lee, and D. Hahn, “Hot
Pool Model for a Stratified Volume Calculation in a Pool-type LMFBR,”
Proceedings of ICAPP ’05: International Congress on Advances in Nuclear Power
Plants, Paper 5666, Seoul, Korea, May 15-19, 2005.
31. J. E. Cahalan, D. Hahn, W. P. Chang, and Y. M. Kwon, “Passive Safety
Optimization in Liquid-Sodium Cooled Reactors,” Proceedings of NUTHOS-6:
The 6th International Conference on Nuclear Reactor Thermal Hydraulics,
Operation and Safety, Nara, Japan, October 4-8, 2004.
32. Y. M. Kwon, H. Y. Jeong, W. P. Chang, Y. B. Lee, D. Hahn, and J. E. Cahalan,
“Comparative Analysis of the KALIMER ATWS by Using SSC-K and
SAS4A/SASSYS-1,” Proceedings of the KNS Autumn Meeting, Yongpyung,
October 2004.
33. Y. M. Kwon, S. D. Suk, and Y. B. Lee, “Exclusion of Core Disruptive Accident
from Design Basis Accident Envelope in KALIMER,” Proceedings of the KNS
Autumn Meeting, Yongpyung, October 2004.
34. Y. M. Kwon, Y. B. Lee, W. P. Chang, D. Hahn, and C. M. Kang, “Comparative
Analysis of ULOF in the KALIMER Design Using SSC-K and SAS4A/SASSYS-
1 Computer Codes,” Proceedings of NURETH-10: The 10th International Topical
Meeting on Nuclear Reactor Thermalhydraulics, Seoul, Korea, October 5-9, 2003.
35. Y. M. Kwon, Y. B. Lee, and D. Hahn, “Thermal-hydraulic Characteristics of
Local Blockage within a Wire-Wrapped Pin-Bundle Subassembly for
KALIMER,” Proceedings of the KNS Spring Meeting, Kyeongju, May 2003.
36. Y. M. Kwon, Y. B. Lee, W. P. Chang, and D. Hahn, “Inherent Safety of the
KALIMER Breakeven Core Design for Various ATWS Events,” Proceedings of
ICAPP ’03: International Congress on Advances in Nuclear Power Plants, Paper
3208, Cordoba, Spain, May 4-7, 2003.
37. Y. M. Kwon, W. P. Chang, Y. B. Lee, and D. Hahn, “Analysis of Long-Term
Cooling by Passive Decay Heat Removal System for Unprotected Loss of Heat
Sink Event in the KALIMER Design,” Proceedings of ICONE-11: The 11th
International Conference on Nuclear Engineering, Paper 36534, Tokyo, Japan,
April 20-23, 2003.
38. Y. M. Kwon, Y. B. Lee, W. P. Chang, and D. Hahn, “A Simple Reactivity
Feedback Model Accounting for Radial Core Expansion Effects in the Liquid-
Metal Fast Reactor,” Proceedings of the KNS Autumn Meeting, Yongpyung,
October 2002.
39. Y. M. Kwon, Y. B. Lee, W. P. Chang, D. Hahn, and C. M. Kang, “Comparative
Analysis of an Unprotected Transient Overpower Using the SSC-K and
SAS4A/SASSYS-1 Computer Codes,” Proceedings of NTHAS-3: The 3rd Korea-
Japan Symposium on Nuclear Thermal-Hydraulics and Safety, pp.586-591,
Kyeongju, October 13-16, 2002.
40. Y. M. Kwon and D. Hahn, “Thermal-Hydraulic Analysis of Internal Flow
Blockage within Fuel Assembly of Nuclear Liquid-Metal Fast Reactor,”

Proceedings of the 2nd National Congress on Fluid Engineering, Muju, August
2002.
41. Y. M. Kwon, Y. B. Lee, W. P. Chang, D. Hahn, and C. M. Kang “Verification
Study on the SSC-K Computer Code for Evaluating Inherent Safety of Advanced
LMFR,” Trans. Ame. Nucl. Soc., Vol.86, pp.156-157, Hollywood, June 2002.
42. Y. B. Lee, Y. M. Kwon, K. S. Jeong, W. P. Chang, and D. Hahn, “Comparative
Code-to-Code Analysis for Two-Dimensional Hot Pool Model,” Proceedings of
the KNS Spring Meeting, Kwangju, May 2002.
43. Y. M. Kwon, Y. B. Lee, W. P. Chang, and D. Hahn, “Safety Analysis of
KALIMER System with Breakeven Core,” Proceedings of the KNS Spring
Meeting, Kwangju, May 2002. (in Korean)
44. Y. M. Kwon, Y. B. Lee, W. P. Chang, D. Hahn, and C. M. Kang “Comparative
Code-to-Code Analysis for Unprotected Transient Overpower in KALIMER,”
Proceedings of the KNS Spring Meeting, Kwangju, May 2002.
45. Y. M. Kwon, Y. B. Lee, W. P. Chang, and D. Hahn, “A Computer Code for
Evaluating Inherent Safety of an Advanced LMFBR,” Trans. Ame. Nucl. Soc.,
Vol.85, pp.213-214, Reno, November 2001.
46. Y. M. Kwon, K. S. Jeong, Y. B. Lee, W. P. Chang, and D. Hahn, “Inherent Core
Safety of the Korea Advanced Liquid Metal Reactor,” Proceedings of the Korean
Energy Society Autumn Meeting, Daejeon, November 2001.
47. Y. M. Kwon and D. Hahn, “Prediction of Very High Critical Heat Flux for
Subcooled Flow Boiling in a Vertical Round Tube,” Proceedings of the KSME
Autumn Meeting, Jeonju, November 2001.
48. Y. M. Kwon and D. Hahn, “Analysis of Internal Blockage within a Wire-
Wrapped Subassembly for Liquid Metal Fast Breeder Reactor,” Proceedings of
the KNS Autumn Meeting, Daejeon, October 2001.
49. Y. M. Kwon, Y. B. Lee, W. P. Chang, and D. Hahn, “System Transient Analysis
Code for Advanced Liquid Metal Reactor,” Proceedings of the KNS Spring
Meeting, Jeju, May 2001.
50. Y. M. Kwon and D. Hahn, “Design Concept and Selection of Safety Related
Design Bases Events for Improving Safety of KALIMER,” Proceedings of the
Korean Energy Society Spring Meeting, Seoul, May 2001. (in Korean)
51. K. S. Jeong, Y. M. Kwon, and Y. B. Lee, “Simulator Development for the
Transient Analysis in Korea Advanced Liquid Metal Reactor,” Proceedings of the
KSME Conference on Energy and Power, Daejeon, October 2000.
52. Y. M. Kwon, K. S. Jeong, Y. B. Lee, W. P. Chang, and D. Hahn, “SSC-K
Modeling for the System Transient Analysis in the Korea Advanced Liquid Metal
Reactor,” Proceedings of the KSME Conference on Energy and Power, Daejeon,
October 2000.
53. Y. M. Kwon, K. S. Jeong, Y. B. Lee, W. P. Chang, and D. Hahn, “An Effect of
Gas Expansion Module on the Inherent Safety of the Korea Advanced Liquid
Metal Reactor,” Proceedings of the KNS Autumn Meeting, Daejeon, October
2000.
54. Y. M. Kwon and S. H. Chang, “Evaluation of Very High CHF for Subcooled
Flow Boiling Using an Artificial Neural Network and Mechanistic Models,”
Proceedings of the KNS Autumn Meeting, Daejeon, October 2000.

55. Y. B. Lee, Y. M. Kwon, W. P. Chang, K. S. Jeong, and D. Hahn, “Analysis of
Thermo-hydraulic Phenomena in the Hot Pool of KALIMER Design,”
56. W. P. Chang, Y. M. Kwon, Y. B. Lee, K. S. Jeong, and D. Hahn, “Development
of Long Term Cooling Analysis Model for ULOHS Accident in KALIMER,”
57. Y. M. Kwon, Y. B. Lee, W. P. Chang, and D. Hahn, “Analysis of Unprotected
Loss of Flow Accidents in Preliminary Conceptual Design of KALIMER,”
Proceedings of NTHAS-2: The 2nd Korea-Japan Symposium on Nuclear
Thermal-Hydraulics and Safety, Fukuoka, Japan, October 15-18, 2000.
58. Y. M. Kwon, Y. B. Lee, W. P. Chang, and D. Hahn, “SSC-K Computer Code for
Inherent Safety Evaluation of Liquid Metal Reactor,” Proceedings of the 4th
Japan-Korea Seminar on Advanced Reactors, Tokyo, Japan, October 19-20, 2000.
59. Y. M. Kwon and S. H. Chang, “Evaluation of Mechanistic Critical Heat Flux
Models for Subcooled Water Flow Boiling in Round Tube,” Proceedings of the 1 st
National Congress on Fluid Engineering, Muju, September 2000.
60. W. P. Chang, Y. M. Kwon, Y. B. Lee, I. C. Kim, and D. Hahn, “Assessment of
Long Term Cooling Capability of KALIMER,” Proceedings of the KNS Spring
Meeting, Kori, May 2000.
61. Y. B. Lee, Y. M. Kwon, W. P. Chang, S. K. Choi, and D. Hahn, “Development of
the Two-Dimensional Hot Pool Model for Pool-Type Liquid Metal Reactors,”
Proceedings of the KNS Spring Meeting, Kori, May 2000.
62. Y. M. Kwon and D. Hahn, “Safety Issues of the Subassembly Accident in the
Liquid Metal Fast Reactor,” Proceedings of the KNS Spring Meeting, Kori, May
2000. (in Korean)
63. Y. M. Kwon and S. H. Chang, “Evaluation of Prediction Models for Subcooled
Water Flow Boiling CHF for High-Heat-Flux Applications,” ICONE-8: The 8th
International Conference on Nuclear Engineering, Paper 8431, Baltimore, USA,
April 2-6, 2000.
64. Y. M. Kwon, I. C. Kim, W. P. Chang, and D. Hahn, “Safety Evaluation of
Preliminary KALIMER Design during an Unprotected Loss of Flow Event,”
ICONE-8: The 8th International Conference on Nuclear Engineering, Paper 8439,
Baltimore, USA, April 2-6, 2000.
65. Y. M. Kwon, I. C. Kim, W. P. Chang, and D. Hahn, “Preliminary Safety
Evaluation of KALIMER Conceptual Design with Uranium Metal Core during an
Unprotected Loss of Flow Accident,” Proceedings of the KNS Autumn Meeting,
Seoul, October 1999.
66. Y. M. Kwon, I. C. Kim, and S. H. Chang, “Evaluation of High-Heat-Flux
Subcooled Flow Boiling CHF Using Mechanistic Models,” Proceedings of the
KNS Autumn Meeting, Seoul, October 1999.
67. Y. M. Kwon, S. D. Suk, and S. H. Chang, “A Mechanistic Critical Heat Flux
Model for Subcooled Flow Boiling Using a Rough-Wall Analogy of Bubbles
Attached on the Wall,” Proceedings of the 2nd International Symposium on Two-
phase Flow Modeling and Experimentation, Pisa, Italy, May 23-26, 1999.

68. Y. M. Kwon, D. Hahn, and S. H. Chang, “Prediction of Critical Heat Flux in
Highly Subcooled Flow Boiling with High Mass Velocity and Small Diameter,”
Proceedings of the KNS Spring Meeting, Pohang, May 1999.
69. Y. M. Kwon, D. Hahn, and S. D. Suk, “Safety Related Design Bases Events and
Analysis Methodology for KALIMER,” Proceedings of the KNS Spring Meeting,
Pohang, May 1999. (in Korean)
70. D. Hahn, Y. M. Kwon, K. D. Kim, and W. P. Chang, “Preliminary Safety
Evaluation of KALIMER under Transient Overpower Accident,” Proceedings of
the KNS Spring Meeting, Pohang, May 1999.
71. Y. M. Kwon, S. D. Suk, and S. H. Chang, “Prediction of Critical Heat Flux in
Highly Subcooled Convective Boiling,” Proceedings of NURETH-9: The 9th
International Topical Meeting on Nuclear Reactor Thermal Hydraulics, San
Francisco, 1999.
72. D. Hahn, Y. M. Kwon, K. D. Kim, W. P. Chang, and S. D. Suk, “Safety
Performance of Preliminary KALIMER Conceptual Design,” Proceedings of
ICONE-7: The 7th International Conference on Nuclear Engineering, Kyoto,
1999.
73. D. Hahn, W. P. Chang, and Y. M. Kwon, “Inherent Safety Performance of
KALIMER Design Concept,” Proceedings of '99 International Conference on
Future Nuclear Systems Nuclear Technology, Wyoming, 1999.
74. K. D. Kim, Y. M. Kwon, D. Hahn, W. P. Chang, and S. D. Suk, “Development of
the Best-estimate System Transient Analysis Code,” SSC-K, for Pool-Type
Liquid Metal Reactors” Proceedings of the KNS Autumn Meeting, Seoul, October
1998.
75. Y. M. Kwon, S. D. Suk, and S. H. Chang, “Developments in Predicting
Subcooled Flow Boiling CHF,” Proceedings of the KNS Autumn Meeting, Seoul,
October 1998.
76. D. H. Hahn, Y. M. Kwon, K. D. Kim, W. P. Chang, and S. D. Suk, “Inherent
Safety Evaluation Models of SSC-K Code,” Proceedings of the KNS Autumn
Meeting, Seoul, October 1998.
77. W. P. Chang, Y. M. Kwon, K. D. Kim, D. Hahn, and S. D. Suk, “PSDRS Model
for KALIMER System Code SSC-K,” Proceedings of the KNS Autumn Meeting,
Seoul, October 1998.
78. Y. M. Kwon, S. D. Suk, and S. H. Chang, “Two-Phase Flow Modeling of Critical
Heat Flux for Subcooled and Low Quality Flow Boiling,” Proceedings of
NTHAS98: the 1st Korea-Japan Symposium on Nuclear Thermal-Hydraulics and
Safety, Pusan, Korea, pp.395-401, October 21-24, 1998.
79. Y. M. Kwon and S. H. Chang, “Theoretical Prediction of Subcooled Flow Boiling
CHF,” Proceedings of the KNS Spring Meeting, pp.449-456, May 1998.
80. Y. M. Kwon and D. Hahn, “Simulation of Unprotected-Loss-of-Flow Event Using
DSNP Code,” Proceedings of the KNS Spring Meeting, pp.738-744, May 1998.
81. Y. M. Kwon and S. H. Chang, “An Improved Mechanistic Critical Heat Flux
Model for Subcooled Flow Boiling,” Proceedings of the KNS Autumn Meeting,
pp.552-557, October 1997.

82. Y. M. Kwon et. al. “Safety Depressurization System for Korean Next Generation
Reactor,” Proceedings of the 2nd International Conference on Advanced Reactor
Safety, Orlando, Florida, pp.1294-1301, June 1997.
83. Y. M. Kwon and J. H. Song “Realistic LOCA Containment Analysis Using a
Merged Version of RELAP5/CONTEMPT4,” Proceedings of NUTHOS-5: The
5th International Topical Meeting on Nuclear Thermal Hydraulics, Operation, &
Safety, Beijing, China, GG3, April 1997.
84. Y. M. Kwon, H.S. Lim, and J. H. Song “Rapid Depressurization Capability of
Monobloc SEBIM Valves for KNGR Total Loss of Feedwater,” Proceedings of
the KNS Autumn Meeting, pp.389-394, November 1996.
85. Y. M. Kwon, J. H. Song, and K. Y. Lee “Realistic LOCA Containment Analysis
Using a Merged Version of RELAP5/CONTEMPT4,” Proceedings of the KNS
Spring Meeting, pp.447-452, May 1996.
86. Y. M. Kwon, J. H. Song, and J. K. Park “Review on the Safety Analysis
Methodology for Common Mode Failure of Reactor Protection System,”
Proceedings of the KNS Spring Meeting, pp.333-339, May 1996.
87. Y. M. Kwon, J. Y. Hur et al. “Proposal for the Reduction of Containment Mass
and Energy Release during a Large Break Loss of Coolant Accident,”
Proceedings of the KNS Spring Meeting, pp.399-404, May 1996.
88. Y. M. Kwon, and J. H. Song et. al. “Containment Response for the Double Ended
Hot Leg LOCA of the YGN 3&4,” Proceedings of the KNS Spring Meeting,
pp.509-516, May 1995.
89. Y. M. Kwon, J. H. Song, S. Y. Lee and S. K. Lee “Mitigation of Total Loss of
Feedwater Event by Using Safety Depressurization System,” Technical
Committee Meeting on Progress in Design, Research & Development and Testing
of Safety System for Advanced Water Cooled Reactors, Picenza, Italy, IAEA-
TECDOC-872, pp.113-122, May 1995.
90. Y. M. Kwon, J. H. Song, and T. S. Ro “Sensitivity of Break-Flow-Partition on the
Containment Pressure and Temperature,” Proceedings of the KNS Autumn
Meeting, pp.361-366, October 1994.
91. Y. M. Kwon, J. H. Song, and T. S. Ro “Numerical Simulation of Total Loss of
Feedwater Event Using RELAP5/MOD3,” Proceedings of the KNS Autumn
Meeting, pp.411-416, October 1994.
92. Y. M. Kwon, J. H. Song, and T. S. Ro “Comparative Simulation of Total Loss of
Feedwater Event Using RELAP5/MOD3 and CEFALSH-4AS/REM Computer
Codes,” Proceedings of the 3rd JSME-KSME Fluids Engineering Conference,
Sendai, Japan, pp.7-13, July 1994.
93. Y. M. Kwon, J. H. Song, and T. S. Ro “Long Term Feed and Bleed Operation of
Safety Depressurization System for Total Loss of Feedwater Event in PWR,”
Proceedings of the 6th International Symposium on Transport Phenomena and
Thermal Engineering, Seoul, pp.331-336, May 1993.
94. Y. M. Kwon, J. H. Song, and T. S. Ro “Decay Heat Removal Capability of Safety
Depressurization System for Total Loss of Feedwater Event,” Proceedings of
NURETH-5: The 5th International Topical Meeting on Nuclear Reactor
Thermalhydraulics, Salt Lake City, Utah, Vol.6, pp.1812-1818, September 1992.

95. Y. M. Kwon, J. H. Song, and T. S. Ro “Rapid Depressurization Capability of
Safety Depressurization System for Total Loss of Feedwater Event,” Proceedings
of the KNS Spring Meeting, pp.177-184, May 1992.
96. Y. M. Kwon, J. H. Song, and T. S. Ro “Study of Containment Back-Pressure on
the Mass and Energy Release for LB-LOCA,” Proceedings of the KNS Spring
Meeting, pp.743-753, May 1990.

Technical Reports:

1. Y. M. Kwon, A Report on the Negative Reactivity Transient Model in SSC-K
Code, SFR Safety and Operation Project, GiF
2. Y. M. Kwon et al., Unprotected Accident Analyses of the 1200MWe GEN-IV
Sodium-Cooled Fast Reactor Using the SSC-K Code, KAERI/TR-4019/2010,
Korea Atomic Energy Research and Institute, February 2010.
3. Y. I. Kim, Y. M. Kwon et al., Core Design Studies for TRU Transmutation in a
Sodium Cooled Fast Reactor, International Nuclear Energy Research Initiative
Project 2006-2009, September 2009.
4. Y. M. Kwon et al., Review of Phenomenological Models for the Initial Phase
HCDA Analysis in a Metal-Fueled Sodium-Cooled Fast Reactor, KAERI/TR-
3748/2009, Korea Atomic Energy Research and Institute, March 2009.
5. Y. M. Kwon et al., Inherent Passive Safety Characteristics of a Sodium-Cooled,
Metal-Fueled, Pool-Type Fast Reactor, KAERI/TR-3727/2009, Korea Atomic
Energy Research and Institute, February 2009.
6. Y. M. Kwon et al., Doppler Reactivity Feedback Model for Metal-fueled Liquid
Metal Fast Reactor, KAERI/TR-3531/2008, Korea Atomic Energy Research
and Institute, January 2008.
7. Y. M. Kwon et al., Control Rod Driveline Reactivity Feedback Model for
Liquid Metal Fast Reactor, KAERI/TR-3532/2008, Korea Atomic Energy
Research and Institute, January 2008.
8. D. Hahn, Y. M. Kwon et al., KALIMER-600 Conceptual Design Report,
KAERI/TR-3381/2007, Korea Atomic Energy Research and Institute, February
2007.
9. Y. M. Kwon et al., Evaluation of the Inherent Safety Features of the
KALIMER-600 Design Concept for Anticipated Transient without Scram
Events, KAERI/TR-3163/2006, Korea Atomic Energy Research and Institute,
March 2006.
10. Y. B. Lee, Y. M. Kwon et al., Safety Analysis for Key Design Features of
KALIMER-600 Design Concept, KAERI/TR-2968/2006, Korea Atomic Energy
Research and Institute, March 2006.
11. Y. M. Kwon et al., A Plan for the Development of the Spatial Kinetics and the
Detailed Reactivity Model for a Fast Reactor, KAERI/TR-3071/2005, Korea
Atomic Energy Research and Institute, November 2005.

12. Y. M. Kwon et al., Evaluation of Inherent Safety of the KALIMER-150 Design
using the SAS4A/SASSYS-1 Computer Code, KAERI/TR-2935/2005, Korea
Atomic Energy Research and Institute, February 2005.
13. D. Hahn, Y. M. Kwon, KALIMER-600 Design Concept Report, KAERI/TR-
2784/2004, Korea Atomic Energy Research and Institute, February 2004.
14. Y. M. Kwon et al., Comparative Analysis of an Unprotected Loss of Flow
Transient in the KALIMER Design Using the SSC-K and the SAS4A/SASSYS-
1 Computer Codes, KAERI/TR- /2003, Korea Atomic Energy Research and
Institute, July 2003.
15. Y. M. Kwon et al., Comparative Analysis of an Unprotected Overpower
Transient in the KALIMER Design Using the SSC-K and the SAS4A/SASSYS-
1 Computer Codes, KAERI/TR-2203/2002, Korea Atomic Energy Research and
Institute, June 2002.
16. Y. M. Kwon et al., SSC-K Code User’s Manual, Rev.1, KAERI/TR-2014/2002,
Korea Atomic Energy Research and Institute, January 2002.
17. D. Hahn, Y. M. Kwon et al., Safety Analysis for Key Design Features of
KALIMER with Breakeven Core, KAERI/TR- /2002, Korea Atomic Energy
Research and Institute, April 2002.
18. Y. M. Kwon and D. Hahn, Development of Safety Analysis Basis for
KALIMER Conceptual Design, KAERI/TR-1957/2001, Korea Atomic Energy
Research and Institute, November 2001.
19. D. Hahn, Y. M. Kwon et al., Preliminary Safety Analysis for Key Design
Features of KALIMER with Breakeven Core, KAERI/TR-1849/2001, Korea
Atomic Energy Research and Institute, June 2001.
20. Y. M. Kwon et al., Analysis of Local Subassembly Accident in KALIMER,
KAERI/TR-1659/2000, Korea Atomic Energy Research and Institute, October
2000.
21. Y. M. Kwon et al., Development of the Component Models for the KALIMER
Safety Analysis Code SSC-K, KAERI/TR-1326/99, Korea Atomic Energy
Research and Institute, May 1999.
22. K. D. Kim, Y. M. Kwon et al., Development of Thermal-Hydraulic System
Analysis Code SSC-K for Pool-Type Liquid Metal Reactor, KAERI/TR-
1266/99, Korea Atomic Energy Research and Institute, March 1999.
23. D. Hahn, Y. M. Kwon et al., Reactivity Feedback Models for SSC-K,
KAERI/TR-1105/98, Korea Atomic Energy Research and Institute, June 1998.
24. Y. M. Kwon, et al., Simulation of Unprotected Loss-of-Flow Accident Using
DSNP Code: EBR-II SHRT-45 Test, KAERI/TR-986/98, Korea Atomic Energy
25. K. D. Kim, Y. M. Kwon et al., Review of Existing Models and Development of
New Models for SSC-K Code, KAERI/TR-990/98, Korea Atomic Energy
26. J. H. Song, Y. M. Kwon et al., “Development of small and medium integral
reactor: safety analysis for small and medium size,” KAERI/RR-1747/96,
October 1997.

27. Y. M. Kwon et al., An Analysis Methodology for Hot Leg Break Mass and
Energy Release, KAERI/TR-746/96, Korea Atomic Energy Research and
Institute, July 1996.
28. Y. M. Kwon et al., Technical Manual for Combined Mass and Energy Release
Analysis Tool (COMET), KAERI/TR-747/96, Korea Atomic Energy Research
and Institute, July 1996.
29. Y. M. Kwon et al., Development of Analysis Methodology for Hot Leg Break
Mass and Energy Release, KAERI/TR-507/95, Korea Atomic Energy Research
and Institute, April 1995.
30. Y. M. Kwon, Evaluation of Decay Heat Removal Capability of Safety
Depressurization System for Total Loss of Feedwater Event,” KAERI/Senior-
Researcher, Korea Atomic Energy Research and Institute, 1991.

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