NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 4921 to 4940 of 5619

4921
CRX-Hex : A Transport Theory Code Based on Characteristic Method for Hexagonal Geometry

Cho, Nam-Zin; Hong, S.G, Proc. of the Korean Nuclear Society Spring Meeting, pp.28 - 33, 1996-05

4922
Design Charateristics of Moderation- Enhanced Reactor Core Loaded 100% with MOX Fuel

Kim, Y.B; Cho, Nam-Zin, KAIF/KNS Annual Conference, 1996-03

4923
CRX : A Characteristic Transport Theory Code for Cell and Assembly Calculations in Reactor Core Design

Cho, Nam-Zin; Hong, S.G., Proc. of the Korean Nuclear Society Autumn Meeting, pp.85 - 90, 1995-10

4924
A Multigroup Diffusion Nodal Scheme : Hybrid of AFEN and PEN Methods

Cho, Nam-Zin; Noh, J.M., Proc. of the Korean Nuclear Society Autumn Meeting, pp.29 - 34, 1995-10

4925
Development of a Three-Dimensional Nodal Diffusion Code Based on the AFEN Methodology

Hong, S.G; Cho, Nam-Zin; Noh, J.M., Proc. of the Korean Nuclear Society Spring Meeting, pp.77 - 82, 1995-05

4926
On the AFEN Method for Triangular Nodes in Hexagonal Assembly Cores

Cho, Nam-Zin; Kim, D.S., Proc. of the Korean Nuclear Society Spring Meeting, pp.25 - 30, 1995-05

4927
The Nodal Methods in Reactor Core Nuclear Design

Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.45 - 53, 1995-05

4928
Characteristics of Dynamic Strain Anging(DSA) in SA106GR.C Piping Steel

김인섭, Proc. of the Korean Nuclear Society Autumn Meeting, pp.771 - 776, 1995

4929
열처리가 Zr-2.5Nb 압력관재료의 지체균열전파에 미치는 영향

김인섭, Proc. of the Korean Nuclear Society Autumn Meeting, pp.765 - 770, 1995

4930
Compact Test Generation Of Robustly Hazard-Free Tests For Path Delay Fault In Combinational Circuits Using 19-Valued Logic

Kim, Dae Sik; Seong, Poong-Hyun, Maintenance And Reliability Conference, pp.24 - 24, 1997-05

4931
Development of a Charge Collection Model in CdZnTe Detectors and its Application to Gamma Spectrum

Cho, Gyuseong; Kim, YS; Joo, KS, International Synposium on Solid State Detectors for the 21st Century, 1998

4932
Analysis of the Void Wave Propagations : Wave Number Independent Characteristicse

No, Hee Cheon; Song, Chul Hwa; Chung, Moon Ki, Proc. of the 7th Int'l Met. on Nuclear Reactor Thermal-Hydraulics(NURETH-7), 1995

4933
The Effect of Bubble Flow Structures on the void Wave Propagations in a Large Diameter Pope

No, Hee Cheon; Song, CH; Chung, MK, Proceedings of the International Confefence on Multiphase Flow, 1995

4934
Comprehensive Promotion Plan for Utilization Research and Development of Nuclear Energy in Korea.

Lee, Kun Jai, Proceedings of the Int'l Symp. "Energy Future in the Asia/Pacific Region"., pp.31 - 42, 1998

4935
Evaluation of Thermal Embrittlement of Duplex Stainless Steel Using Small Punch Test Method

김인섭, 2nd Seminar on Nuclear Materials and Technology, KAERI, 1996

4936
SA106Gr.C 주증기 배관재의 피로균열성장에 미치는 후열처리의 영향

김인섭, 국내원전기기의 건전성평가기술 워크샵, 1996

4937
자기적 성질변화를 이용한 원자로 압력용기강의 조사효과평가

김인섭, Proc. of the Korean Nuclear Society Spring Meeting, pp.317 - 322, 1996

4938
Accoustic Emission Behavior During Stress Corrosion Crcking of Inconel 600

김인섭, Proc. of the Korean Nuclear Society Spring Meeting, pp.145 - 150, 1996

4939
Fatigue Crack Propagation Behavior in Butt Weldment of SA106Gr.C Main Steam Pipe Steel

김인섭, Proc. of the Korean Nuclear Society Spring Meeting, pp.92 - 97, 1996

4940
Small Punch Test for the Evaluation of Thermal Aging Embrittlement of CF8 Duplex Stainless Steel

김인섭, Proc. of the Korean Nuclear Society Autumn Meeting, pp.79 - 84, 1996

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