NE-Journal Papers(저널논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 2201 to 2220 of 2796

2201
Graphite-Filled MOX Fuel Design for Fully Loaded PWR Cores

Jo, C.K; Cho, Nam-Zin; Kim, Y.H, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.78, pp.227, 1998

2202
Using the LEPRICON System To Evaluate Best-Estimate Vessel Fluence at Ulchin NPP Unit 1

Cho, Nam-Zin; Kim, H.H.; Hwang, H.R., TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.82, pp.216, 2000-06

2203
Benefit Assessment of Using In-Core Neutron Detector Signals in CPCS

Han, Seung; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.74, pp.271 - 272, 1996-06

2204
Design of a Low Power Reactor with High Quality Neutron Beams for BNCT

Park, J.H; Cho, Nam-Zin, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.80, pp.71, 1999-06

2205
Low temperature synthesis of PbTiO3 thin films by MOCVD without carrier gas

Byun, C; Jang, JW; Cho, YJ; Lee, Kun Jai; Lee, BW, THIN SOLID FILMS, v.324, no.1-2, pp.94 - 100, 1998-07

2206
Knowledge Acquisition for NPP Knowledge-Based Systems Using Document Analysis

Park, Joo Hyun; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.70, pp.107 - 108, 1997

2207
Prediction of Software Operational Reliability Using Testing Environment Factors

Jung, HS; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.73, pp.143 - 146, 1995

2208
Prediction of Safety Critical Software Operational Reliability from Test Reliability Using Environment Factors

Jung, Hoan-Sung; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND TECHNOLOGY , v.31, no.1, pp.49 - 57, 1999-02

2209
Prediction of the Volume of Solid Radioactive Wastes to be Generated from Korean Next Generation Reactor

Cheong, Jae-Hak; Lee, Kun-Jai; Maeng, Sung-Jun; Song, Myung-Jae; Park, Kyu-Wan, 원자력학회지, v.29, no.3, pp.218 - 228, 1997

2210
Criticality calculation for cluster fuel bundles using grey Dancoff factor

Kim, HH; Cho, Nam-Zin, ANNALS OF NUCLEAR ENERGY, v.26, no.9, pp.803 - 820, 1999-06

2211
후행핵연료주기 정책 현황

이건재; 정재학, 한국화학공학회지, v.16, no.3, pp.201 - 206, 1998-05

2212
Electrical circuit model for quantifying the proliferation resistance of nuclear fuel cycles

Ko, WI; Kim, HD; Yang, MS; Park, HS; Lee, Kun Jai, ANNALS OF NUCLEAR ENERGY, v.27, no.15, pp.1399 - 1425, 2000-10

2213
Legendre polynomial expansion method for evaluating multipole moments of current density in toroidal devices

Seo, SH; Kim, J; Huh, SH; Choe, Wonho; Chang, Hong-Young; Jeong, SH, PHYSICS OF PLASMAS, v.7, no.5, pp.1487 - 1493, 2000-05

2214
Pressurized thermal shock analyses of a reactor pressure vessel using critical crack depth diagrams

Jhung, MJ; Park, YW; Jang, Changheui, INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, v.76, no.12, pp.813 - 823, 1999-10

2215
Uncertainty Analysis in Dupic Fuel-Cycle Cost Using a Probabilistic Simulation Method

Ko, W.I.; Choi, J.W.; Lee, J.S.; Park, H.S.; Lee, Kun Jai, NUCLEAR TECHNOLOGY, v.127, no.1, pp.123 - 140, 1999-07

2216
Polydispersed Colloid Transport in Porous Media : An Experiment and Modelling

최희주; 이건재, 한국원자력학회지, v.27, no.1, pp.1 - 7, 1995-02

2217
Interfacial Wave Characteristics for Countercurrent Stratified Air-Water Flow in a Horizontal Pipe

Chung, Heung-June; Chun, Se-Young; Chung, Moon-Ki; No, Hee-Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.28, no.4, pp.379 - 389, 1996-08

2218
Implementation of a Dynamic Safety System in a PLC for PWRs

Kim, Ung Soo; Kang, Hyun Gook; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.76, pp.314 - 314, 1997

2219
ASSESSMENT OF WATER-FILLED BOREHOLE AS A PREFERRED PATHWAY PENETRATING RADIOACTIVE-WASTE REPOSITORY

Choi, HJ; Lee, Kun Jai; KIM, CL, ANNALS OF NUCLEAR ENERGY, v.22, no.3-4, pp.249 - 260, 1995-03

2220
Second-order model for free surface convection and interface reconstruction

Kim, SO; No, Hee Cheon, INTERNATIONAL JOURNAL FOR NUMERICAL METHODS IN FLUIDS, v.26, no.1, pp.79 - 100, 1998-01

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