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Subject index of Volume 212
Nuclear Engineering and Design 212 (2002) 417– 418 www.elsevier.com/locate/nucengdes
Subject Index of Volume 212 Engineering Mechanics Probabilistic fracture mechanics analysis for pipe considering dispersion of seismic loading H. Machida, M. Arakawa and Y. Kamishima Development of flaw evaluation guideline for FBR components N. Miura, Y. Nakayama and Y. Takahashi Modelling the early development of secondary side stress corrosion cracks in steam generator tubes using incomplete random tessellation L. Cizelj and H. RieschOppermann 2D crack growth simulation with an energetic approach S. Marie and S. Chapuliot Structural integrity assessment of pressure tubes for Wolsong Unit 1 based on operational experiences Y.W. Park, S.S. Kang and B.S. Han Estimation of fracture toughness transition curves of RPV steels from Charpy impact test data S.H. Kim, Y.W. Park, S.S. Kang and H.D. Chung Dynamic fracture toughness test and master curve method analysis of IAEA JRQ material K.K. Yoon and K. Hour The fracture behaviour of cast steel and its prediction based on the local approach V. Koza´k, I. Dlouhy´ and M. Holzmann Modelling of thermal and flow stratification for reactor pressure vessel pressurised thermal shock H.G. Lele, S.K. Gupta, H.S. Kushwaha and V. Venkat Raj Leak rates through cracks and slits in PHT pipes for LBB
PII: S 0 0 2 9 - 5 4 9 3 ( 0 2 ) 0 0 0 5 7 - 2
212 (2002) 1
212 (2002) 13
212 (2002) 21
212 (2002) 31
212 (2002) 41
212 (2002) 49
212 (2002) 59
212 (2002) 67
212 (2002) 75
B. Ghosh, S.K. Bandyopadhyay, S.K. Gupta, H.S. Kushwaha and V. Venkat Raj Assessment of integrity of components in piping of 500 MWe PHWR: using R-6 method R. Rastogi, V. Bhasin, K.K. Vaze and H.S. Kushwaha Probabilistic fracture analysis of a straight pipe with through-wall circumferential crack using R6 method R. Rastogi, V. Bhasin, K.K. Vaze and H.S. Kushwaha Some issues by using the master curve concept H.-W. Viehrig, J. Boehmert and J. Dzugan A comparison between Japanese and French A16 defect assessment procedures for fatigue crack growth T. Wakai, C. Poussard and B. Drubay The effect of internal pressure on in-plane collapse moment of elbows J. Chattopadhyay Time history nonlinear earthquake response analysis considering materials and geometrical nonlinearity T. Kobayashi, K. Yoshikawa, E. Takaoka, M. Nakazawa and Y. Shikama Estimation of crack driving forces on strength-mismatched bimaterial interfaces H. Lee Estimation of historical earthquake intensities and intensity– PGA relationship for wooden house damages I.-K. Choi and J.-M. Seo Structural integrity evaluation method for overheating rupture of FBR steam generator tube H. Machida, N. Yoshioka and H. Ogo
212 (2002) 85
212 (2002) 99
212 (2002) 109
212 (2002) 115
212 (2002) 125
212 (2002) 133
212 (2002) 145
212 (2002) 155
212 (2002) 165
212 (2002) 183
418
Subject Index / Nuclear Engineering and Design 212 (2002) 417–418
Simplified estimation method for first excursion probability of secondary system with gap S. Aoki Development of core seismic analysis models for KNGR fuel assemblies associated with 0.3 g seismic loads H.K. Kim and J.S. Lee Vertical seismic response of overhead crane A. Otani, K. Nagashima and J. Suzuki Development of high-performance concrete having high resistance to chloride penetration B.H. Oh, S.W. Cha, B.S. Jang and S.Y. Jang Thermo-physical properties and transient heat transfer of concrete at elevated temperatures K.-Y. Shin, S.-B. Kim, J.-H. Kim, M. Chung and P.-S. Jung Flaw evaluation of Japanese carbon steel piping by load curve approach K. Kashima Evaluation of seismic fragility of structures—a case study K. Bharga6a, A.K. Ghosh, M.K. Agrawal, R. Patnaik, S. Ramanujam and H.S. Kushwaha A structural analysis of the circular cylinder with multi holes under thermal loading Y.S. Lee, M.H. Choi, Y.H. Kang and D.S. Shin Structural response function approach for evaluation of thermal striping phenomena N. Kasahara, H. Takasho and A. Yacumpai
.
212 (2002) 193
212 (2002) 201
212 (2002) 211
212 (2002) 221
212 (2002) 233
212 (2002) 243
212 (2002) 253
212 (2002) 273
212 (2002) 281
Shaking table tests on failure characteristics of base isolation system for a DFBR plant N. Sato, A. Kato, Y. Fukush-ima and M. Iizuka Development of an intelligent system for ultrasonic flaw classification in weldments S.-J. Song, H.-J. Kim and H. Cho Hexahedral mesh generation of nuclear structures using intelligent local approach Y. Wada and S. Yoshimura Elastic – plastic analysis of nuclear structures with millions of DOFs using the hierarchical domain decomposition method T. Miyamura, H. Noguchi, R. Shioya, S. Yoshimura and G. Yagawa Ultimate capacity analysis of 1/4 PCCV model subjected to internal pressure K. Yonezawa, K. Imoto, Y. Watanabe and M. Akimoto Reanalysis and evaluation of the seismic capacity of the CANDU 700 MW NPP CERNAVODA I. Rotaru, V. Serban, N.J. Krutzik, D. Papandreou and W. Schu¨ tz Primary water stress corrosion cracking behaviors in the shot-peened Alloy 600 TT steam generator tubings I.-G. Park Thermo-mechanical FE-analysis of residual stresses and stress redistribution in butt welding of a copper canister for spent nuclear fuel L.-E. Lindgren, H.A, . Ha¨ ggblad, B.L. Josefson and L. Karlsson
212 (2002) 293
212 (2002) 307
212 (2002) 321
212 (2002) 335
212 (2002) 357
212 (2002) 381
212 (2002) 395
212 (2002) 401
Subject Index of Volume 212 Engineering Mechanics Probabilistic fracture mechanics analysis for pipe considering dispersion of seismic loading H. Machida, M. Arakawa and Y. Kamishima Development of flaw evaluation guideline for FBR components N. Miura, Y. Nakayama and Y. Takahashi Modelling the early development of secondary side stress corrosion cracks in steam generator tubes using incomplete random tessellation L. Cizelj and H. RieschOppermann 2D crack growth simulation with an energetic approach S. Marie and S. Chapuliot Structural integrity assessment of pressure tubes for Wolsong Unit 1 based on operational experiences Y.W. Park, S.S. Kang and B.S. Han Estimation of fracture toughness transition curves of RPV steels from Charpy impact test data S.H. Kim, Y.W. Park, S.S. Kang and H.D. Chung Dynamic fracture toughness test and master curve method analysis of IAEA JRQ material K.K. Yoon and K. Hour The fracture behaviour of cast steel and its prediction based on the local approach V. Koza´k, I. Dlouhy´ and M. Holzmann Modelling of thermal and flow stratification for reactor pressure vessel pressurised thermal shock H.G. Lele, S.K. Gupta, H.S. Kushwaha and V. Venkat Raj Leak rates through cracks and slits in PHT pipes for LBB
PII: S 0 0 2 9 - 5 4 9 3 ( 0 2 ) 0 0 0 5 7 - 2
212 (2002) 1
212 (2002) 13
212 (2002) 21
212 (2002) 31
212 (2002) 41
212 (2002) 49
212 (2002) 59
212 (2002) 67
212 (2002) 75
B. Ghosh, S.K. Bandyopadhyay, S.K. Gupta, H.S. Kushwaha and V. Venkat Raj Assessment of integrity of components in piping of 500 MWe PHWR: using R-6 method R. Rastogi, V. Bhasin, K.K. Vaze and H.S. Kushwaha Probabilistic fracture analysis of a straight pipe with through-wall circumferential crack using R6 method R. Rastogi, V. Bhasin, K.K. Vaze and H.S. Kushwaha Some issues by using the master curve concept H.-W. Viehrig, J. Boehmert and J. Dzugan A comparison between Japanese and French A16 defect assessment procedures for fatigue crack growth T. Wakai, C. Poussard and B. Drubay The effect of internal pressure on in-plane collapse moment of elbows J. Chattopadhyay Time history nonlinear earthquake response analysis considering materials and geometrical nonlinearity T. Kobayashi, K. Yoshikawa, E. Takaoka, M. Nakazawa and Y. Shikama Estimation of crack driving forces on strength-mismatched bimaterial interfaces H. Lee Estimation of historical earthquake intensities and intensity– PGA relationship for wooden house damages I.-K. Choi and J.-M. Seo Structural integrity evaluation method for overheating rupture of FBR steam generator tube H. Machida, N. Yoshioka and H. Ogo
212 (2002) 85
212 (2002) 99
212 (2002) 109
212 (2002) 115
212 (2002) 125
212 (2002) 133
212 (2002) 145
212 (2002) 155
212 (2002) 165
212 (2002) 183
418
Subject Index / Nuclear Engineering and Design 212 (2002) 417–418
Simplified estimation method for first excursion probability of secondary system with gap S. Aoki Development of core seismic analysis models for KNGR fuel assemblies associated with 0.3 g seismic loads H.K. Kim and J.S. Lee Vertical seismic response of overhead crane A. Otani, K. Nagashima and J. Suzuki Development of high-performance concrete having high resistance to chloride penetration B.H. Oh, S.W. Cha, B.S. Jang and S.Y. Jang Thermo-physical properties and transient heat transfer of concrete at elevated temperatures K.-Y. Shin, S.-B. Kim, J.-H. Kim, M. Chung and P.-S. Jung Flaw evaluation of Japanese carbon steel piping by load curve approach K. Kashima Evaluation of seismic fragility of structures—a case study K. Bharga6a, A.K. Ghosh, M.K. Agrawal, R. Patnaik, S. Ramanujam and H.S. Kushwaha A structural analysis of the circular cylinder with multi holes under thermal loading Y.S. Lee, M.H. Choi, Y.H. Kang and D.S. Shin Structural response function approach for evaluation of thermal striping phenomena N. Kasahara, H. Takasho and A. Yacumpai
.
212 (2002) 193
212 (2002) 201
212 (2002) 211
212 (2002) 221
212 (2002) 233
212 (2002) 243
212 (2002) 253
212 (2002) 273
212 (2002) 281
Shaking table tests on failure characteristics of base isolation system for a DFBR plant N. Sato, A. Kato, Y. Fukush-ima and M. Iizuka Development of an intelligent system for ultrasonic flaw classification in weldments S.-J. Song, H.-J. Kim and H. Cho Hexahedral mesh generation of nuclear structures using intelligent local approach Y. Wada and S. Yoshimura Elastic – plastic analysis of nuclear structures with millions of DOFs using the hierarchical domain decomposition method T. Miyamura, H. Noguchi, R. Shioya, S. Yoshimura and G. Yagawa Ultimate capacity analysis of 1/4 PCCV model subjected to internal pressure K. Yonezawa, K. Imoto, Y. Watanabe and M. Akimoto Reanalysis and evaluation of the seismic capacity of the CANDU 700 MW NPP CERNAVODA I. Rotaru, V. Serban, N.J. Krutzik, D. Papandreou and W. Schu¨ tz Primary water stress corrosion cracking behaviors in the shot-peened Alloy 600 TT steam generator tubings I.-G. Park Thermo-mechanical FE-analysis of residual stresses and stress redistribution in butt welding of a copper canister for spent nuclear fuel L.-E. Lindgren, H.A, . Ha¨ ggblad, B.L. Josefson and L. Karlsson
212 (2002) 293
212 (2002) 307
212 (2002) 321
212 (2002) 335
212 (2002) 357
212 (2002) 381
212 (2002) 395
212 (2002) 401