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