NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 4901 to 4920 of 5619

4901
The Development of Environmental Risk Assessment Code for Vitrification Facility in Korea

Lee, Kun Jai, International Symposium on Radiation Safety Management, pp.284 - 294, 1997

4902
Optimization for the Radioactive Waste Treatment System at KORI-2 NPP via Genetic Algorithm

Lee, Kun Jai, International Symposium on Radiation Safety Management, pp.381 - 388, 1997

4903
Monte Carlo Studies of Metal/Phosphor Screen in the Therapeutic X-ray Imaging

Cho, Gyuseong; Kim, Ho Kyung; Chung, Yong Hyun; Lee, Hyoung Koo; Yoon, Sei Chul, Symposium on Radiation Measurements and Applications, 1998

4904
Simulation of Neutral Beam Tomography Using Maximum Entropy Method

Cho, Gyuseong; Lee, Seung Wook; Cho, Yong Sub; Choi, Byong Ho, Symposium on Radiation Measurements and Applications, 1998

4905
Iterative and Non-Iterative Condensation Models for Steam Condensation with Noncondensable Gas in a Vertical Tube

No, Hee Cheon; Park, HS, Proc. of the 1st Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 1998

4906
A Dry-Spot Model for Transition Boiling Heat Transfer in Pool Boiling

No, Hee Cheon; Ha, SJ, Int. Conf. of 11th IHTC, 1998

4907
Improvement of direct contact condensation model of RELAP5/MOD3.1 for passive high-pressure injection system

No, Hee Cheon; Lee, SI, Proc. of the Int. Topical Meeting on Advanced Reactors Safety, pp.983 - 992, 1997

4908
Modification of the Condensation Heat Transfer Model of RELAP5/MOD3.1 for the Simulation of Secondary Condensers

No, Hee Cheon; Kim, HT, Proc. of the Int. Topical Meeting on Advanced reactors Safety, 1997

4909
Post-dryout heat transfer and entrained droplet size at low pressure and low flow conditions

No, Hee Cheon; Jeong, HY, 5th Interrnational Topical Meeting on Nuclear Thermal Hydraulicd, Operation, and Safety, 1997

4910
Gravity injection experiments and direct contact condensation regime map for passive high-pressure injection system

No, Hee Cheon; Lee, Sang Il, Proc. of the 5th International Topical Meeting on Nuclear Thermal Hydraulics, Operation,a nd safety, 1997

4911
Dynamic Aging Effect on Integrity of Nuclear Pressure Vessel Steel

김인섭, 1st Seminar on Nuclear Materials, KAERI, 1995

4912
A New Measure of Uncertainty Importance Based on Distributional Sensitivity Analysis for PSA

전문헌, Proc. of the Korean Nuclear Society Autumn Meeting, Taejon, pp.415 - 420, 1996

4913
An Experimental Investigation of Side-Orifice Effects on Pressure Drop for Single-Phase Flow

전문헌, Proc. of the Korean Nuclear Society Autumn Meeting, Taejon, pp.295 - 300, 1996

4914
Methodology for Estimating the Number of Failed Fuel Rods in Operating PWRs Using Diffusion and Kinetic Models

전문헌, Proc. of the Korean Nuclear Society Autumn Meeting, Taejon, pp.97 - 102, 1996

4915
A dry-spot model of critical heat flux in pool and forced convection boiling

No, Hee Cheon; Ha, SJ, 3rd Int. Conf. on Multiphase Flow, 1998

4916
An experimental study of high pressure steam condensation in a vertical tube of passive secondary condensation system

No, Hee Cheon; Kim, SJ, Proc. of the 1st Korea-Japan Symposium on Nuclear thermal Hydraulics and Safety, pp.321 - 327, 1998

4917
Fast Solution of Linear Systems by Wavelet Transform

Park, C.J; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.282 - 287, 1996-05

4918
A Spectral-Galerkin Nodal Method for Solving the Two-Dimensional Multigroup Diffusion Equations

Cheng, H.W; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.157 - 162, 1996-05

4919
A New Approach to Treating Baffle/Reflector Heterogenity in AFEN Methology

Cho, Nam-Zin; Kim, D.S; Kim, Y.H, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.148 - 153, 1996-05

4920
Extension of AFEN Methodology to Multigroup Problems in Hexagonal-Z Geometry

Cho, Nam-Zin; Kim, Y.H; Park, K.W, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.137 - 141, 1996-05

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