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College of Engineering(공과대학)Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)

NE-Conference Papers(학술회의논문)

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Collection's Items (Sorted by Submit Date in Descending order): 81 to 100 of 5611

81
Development of CHF mapping method for fin structured surface

Choi, Jin Young; No, Hee-Cheon, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015, pp.113 - 126, American Nuclear Society, 2015-08

82
Continuous-energy Monte Carlo method for reactor transient analysis based on quasi-static methods

Jo, Yugwon; Cho, Bumhee; Cho, Nam-Zin, Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, pp.3184 - 3197, American Nuclear Society, 2015-04

83
p-CMFD acceleration and nonoverlapping local/global iterative transport methods with 2-D/1-D fusion kernel

Yuk, Seungsu; Cho, Nam-Zin, 2014 International Conference on Physics of Reactors, PHYSOR 2014, Japan Atomic Energy Agency, JAEA, 2014-09

84
Feasibility of Albedo-corrected parameterized equivalence constants for nodal equivalence theory

Kim, Woosong; Kim, Yonghee, Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, pp.3198 - 3208, American Nuclear Society, 2015-04

85
Design of advanced RPS architecture and reliability analysis using markov model

Son, Gwang Seop; Kim, Dong Hoon; Kang, Hyun Gook, 9th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2015, pp.1515 - 1528, American Nuclear Society, 2015-02

86
Optimization of inspection strategy and status monitoring for standby equipment avaiability enhancement

Shin, Sung Min; Kang, Hyun Gook, 9th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2015, pp.1 - 10, American Nuclear Society, 2015-02

87
Test based reliability quantification method for a safety critical software using finite test sets

Shin, Sung Min; Lee, Sang Hun; Kang, Hyun Gook; Son, Han Seong; Lee, Seung Jun, 9th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2015, pp.2420 - 2429, American Nuclear Society, 2015-02

88
Development of a Bayesian belief network model for quantifying software failure probability of a protection system

Chu, TL; Varuttamaseni, A; Yue, M; Lee, SJ; Eom, HS; Kang, Hyun Gook; Kim, MC; et al, 2015 International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2015, pp.909 - 917, American Nuclear Society, 2015-04

89
Preliminary investigation of fission and surface source iteration scheme in domain decomposition method for whole-core Monte Carlo calculation

Jo, Yugwon; Cho, Nam-Zin, 2014 ANS Winter Meeting and Nuclear Technology Expo, pp.1256 - 1259, American Nuclear Society, 2014-11

90
Comparison of two-temperature homogenized model, harmonic- and volumetric-average thermal conductivity models on transient analysis of fully ceramic microencapsulated fuel

Lee, Yoonhee; Cho, Nam-Zin, 2014 ANS Winter Meeting and Nuclear Technology Expo, pp.1562 - 1565, American Nuclear Society, 2014-11

91
Full submersion criticality accident for low enriched uranium nuclear thermal rockets

Venneri, Paolo; Kim, Yonghee; Husemeyer, Peter; Howe, Stephen, 2014 ANS Winter Meeting and Nuclear Technology Expo, pp.1425 - 1428, American Nuclear Society, 2014-11

92
Out-containment gaseous iodine removal efficiency by alkaline spray

Younus, Irfan; Yim, Man-Sung, 2014 ANS Winter Meeting and Nuclear Technology Expo, pp.986 - 988, American Nuclear Society, 2014-11

93
An investigation on the homogenization of fast reactor fuel assembly

Heo, Woong; Kim, Yonghee, 2014 ANS Winter Meeting and Nuclear Technology Expo, pp.1282 - 1284, American Nuclear Society, 2014-11

94
Application of the BigT burnable absorber to AP1000 core for a soluble boron free operation

Yahya, Mohd Syukri; Kim, Yonghee, 2014 ANS Winter Meeting and Nuclear Technology Expo, pp.1208 - 1210, American Nuclear Society, 2014-11

95
Physics study of nuclear reactors for space and rocket propulsions

Venneri, Paolo; Kim, Yonghee, International Congress on Advances in Nuclear Power Plants: Nuclear Power - A Safe and Sustainable Choice for Green Future, ICAPP 2013, Held with the 28th KAIF/KNS Annual Conference, pp.1761 - 1768, Korean Nuclear Society, 2013-04

96
A physics study on alternative reflectors in a compact sodium-cooled breed-and-burn fast reactor

Hartanto, Donny; Kim, Yonghee, International Congress on Advances in Nuclear Power Plants: Nuclear Power - A Safe and Sustainable Choice for Green Future, ICAPP 2013, Held with the 28th KAIF/KNS Annual Conference, pp.1754 - 1760, Korean Nuclear Society, 2013-04

97
Numerical investigation of a centrifugal compressor for supercritical CO2 as a working fluid

Kim, Seong Gu; Ahn, Yoonhan; Lee, Jekyoung; Lee, Jeong-Ik; Addad, Yacine; Ko, Bockseong, ASME Turbo Expo 2014: Turbine Technical Conference and Exposition, GT 2014, American Society of Mechanical Engineers (ASME), 2014-06

98
Photon crosstalk in pixel array for X-ray imaging

Kim, Myung Soo; Kim, Giyoon; Kang, Dong Uk; Lee, Daehee; Cho, Gyuseong, Hard X-Ray, Gamma-Ray, and Neutron Detector Physics XVI, SPIE, 2014-08

99
Assessment of APR-1400 emergency core cooling system performance for design basis LOCA redefinition

Kang, Dong Gu; Ahn, Seung-Hoon; Chang, Soon Heung; Huh, Byung-Gil; Bang, Young-Seok; Seul, Kwang-Won, 2014 22nd International Conference on Nuclear Engineering, ICONE 2014, American Society of Mechanical Engineers (ASME), 2014-07

100
Single-channel thermal analysis of fully ceramic microencapsulated fuel via two-temperature homogenized model

Lee, Yoonhee; Cho, Nam-Zin; Chung, Sun Kyo, 2014 22nd International Conference on Nuclear Engineering, ICONE 2014, American Society of Mechanical Engineers (ASME), 2014-07

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