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Table of contents of journal: *Nuclear engineering and design

Results: 1-25/225

Authors: Xie, LY
Citation: Ly. Xie, Multi-crack growth/coalescence simulation and its role in passive component leak-before-break concept, NUCL ENG DE, 194(2-3), 1999, pp. 113-122

Authors: Ashley, R Gryffroy, D Maillet, E Tesch, JP
Citation: R. Ashley et al., Analysis of the degradation of a PWR control rod during a loss of coolant accident, using the ICARE2 code, NUCL ENG DE, 194(2-3), 1999, pp. 123-150

Authors: Park, JJ Buksa, JJ Houts, MG Arthur, ED
Citation: Jj. Park et al., Estimates of the service lifetime of 304 stainless steel for use in the blanket region of the LANL ABC system, NUCL ENG DE, 194(2-3), 1999, pp. 151-159

Authors: Ahn, YS Kim, HD Byun, TS Oh, YJ Kim, GM Hong, JH
Citation: Ys. Ahn et al., Application of intercritical heat treatment to improve toughness of SA508 C1.3 reactor pressure vessel steel, NUCL ENG DE, 194(2-3), 1999, pp. 161-177

Authors: Luo, ZP Fu, L Qi, WY
Citation: Zp. Luo et al., The design of the J-type neutron flux distribution measurement system, NUCL ENG DE, 194(2-3), 1999, pp. 179-184

Authors: Hata, K Takeuchi, Y Shiotsu, M Sakurai, A
Citation: K. Hata et al., Natural convection heat transfer from a horizontal cylinder in liquid sodium - Part 2: generalized correlation for laminar natural convection heat transfer, NUCL ENG DE, 194(2-3), 1999, pp. 185-196

Authors: Kussmaul, K
Citation: K. Kussmaul, 25th Water Reactor Safety Information Meeting - Preface, NUCL ENG DE, 194(2-3), 1999, pp. 197-197

Authors: Rosinski, ST Carter, RG
Citation: St. Rosinski et Rg. Carter, EPRI activities to address reactor pressure vessel integrity issues, NUCL ENG DE, 194(2-3), 1999, pp. 199-204

Authors: Chopra, OK Chung, HM Kassner, TF Park, JH Shack, WJ Zhang, J Brust, FW Dong, P
Citation: Ok. Chopra et al., Current research on environmentally assisted cracking in light water reactor environments, NUCL ENG DE, 194(2-3), 1999, pp. 205-223

Authors: Rubin, AM Chen, JT Sewell, R Lambright, J Kazarians, M Nowlen, SP Bohn, MP Chokshi, N
Citation: Am. Rubin et al., An update of preliminary perspectives gained from individual plant examination of external events (IPEEE) submittal reviews, NUCL ENG DE, 194(2-3), 1999, pp. 225-250

Authors: Korsah, K Ewing, PD Kercel, S Wood, RT Antonescu, C Tanaka, T
Citation: K. Korsah et al., Current research results on the technical basis for environmental qualification of safety-related digital I&C hardware in nuclear power plants, NUCL ENG DE, 194(2-3), 1999, pp. 251-257

Authors: Tanaka, TJ Nowlen, SP Antonescu, C
Citation: Tj. Tanaka et al., Recent results of an experimental study on the impact of smoke on digital I & C equipment, NUCL ENG DE, 194(2-3), 1999, pp. 259-269

Authors: Yoon, WH
Citation: Wh. Yoon, The role of research in nuclear regulations: a Korean perspective, NUCL ENG DE, 194(1), 1999, pp. 1-5

Authors: Warren, JW Harrison, DL Agarwal, DC Rochau, GE Nakos, JT Kelly, JE
Citation: Jw. Warren et al., Department of energy's annealing prototype demonstration projects, NUCL ENG DE, 194(1), 1999, pp. 7-18

Authors: Diercks, DR Shack, WJ Muscara, J
Citation: Dr. Diercks et al., Overview of steam generator tube degradation and integrity issues, NUCL ENG DE, 194(1), 1999, pp. 19-30

Authors: Majumdar, S
Citation: S. Majumdar, Prediction of structural integrity of steam generator tubes under severe accident conditions, NUCL ENG DE, 194(1), 1999, pp. 31-55

Authors: Bakhtiari, S Kupperman, DS
Citation: S. Bakhtiari et Ds. Kupperman, Modeling of eddy current probe response for steam generator tubes, NUCL ENG DE, 194(1), 1999, pp. 57-71

Authors: Naus, DJ Oland, CB Ellingwood, BR Hookham, CJ Graves, HL
Citation: Dj. Naus et al., Summary and conclusions of a program addressing aging of nuclear power plant concrete structures, NUCL ENG DE, 194(1), 1999, pp. 73-96

Authors: Galyean, WJ Lui, CH Brown, TD Brownson, DA Gregory, JJ
Citation: Wj. Galyean et al., Accident sequence precursor analysis: level 2/3 model development, NUCL ENG DE, 194(1), 1999, pp. 97-106

Authors: Kussmaul, K
Citation: K. Kussmaul, 24th Water Reactor Safety Information Meeting - Bethesda, Maryland, USA - 21-23 October, 1996 - Preface, NUCL ENG DE, 194(1), 1999, pp. IX-IX

Authors: Hofstotter, P Dittmar, S Maile, K Metzner, KJ
Citation: P. Hofstotter et al., In-service monitoring of piping and vessels in nuclear power plants: report on BMU Study SR 2218, NUCL ENG DE, 193(3), 1999, pp. 233-241

Authors: Okamura, H Ohtani, R Saito, K Kimura, K Ishii, R Fujiyama, K Hongo, S Iseki, T Uchida, H
Citation: H. Okamura et al., Basic investigation for life assessment technology of modified 9Cr-1Mo steel, NUCL ENG DE, 193(3), 1999, pp. 243-254

Authors: Kessler, A Labes, M Schwenk, B
Citation: A. Kessler et al., Replacement of the feedwater piping system in the reactor building outsidethe containment at Philippsburg I nuclear power station, NUCL ENG DE, 193(3), 1999, pp. 255-264

Authors: Siegele, D Hodulak, L Varfolomeyev, I Nagel, G
Citation: D. Siegele et al., Failure assessment of RPV nozzle under loss of coolant accident, NUCL ENG DE, 193(3), 1999, pp. 265-272

Authors: Le Delliou, P Julisch, P Hippelein, K Bezdikian, G
Citation: P. Le Delliou et al., Analysis of a bending test on a full-scale PWR hot leg elbow containing a surface crack, NUCL ENG DE, 193(3), 1999, pp. 273-282
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