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Contents (prelim v-vi)
Nuclear Engineering and Design 272 (2014) iv–v
Contents lists available at ScienceDirect
Nuclear Engineering and Design journal homepage: www.elsevier.com/locate/nucengdes
CONTENTS Engineering Mechanics Structural integrity assessment of the reactor pressure vessel under the pressurized thermal shock loading M. Chen, F. Lu, R. Wang and A. Ren Material Properties Irradiation embrittlement assessment and prediction of Armenian NPP reactor pressure vessel steels A. Kryukov, G. Sevikyan, V. Petrosyan and A. Vardanyan Models for fuel porosity evolution in UO2 under various regimes of reactor operation V.I. Tarasov and M.S. Veshchunov The oxidation behavior of three different zones of welded Incoloy 800H alloy W.S. Chen, W. Kai, L.W. Tsay and J.J. Kai
84
28 65 92
Reactor Engineering A numerical solution to the point kinetic equations using Taylor-Lie series combined with a scaling and squaring technique H.T. Kim, Y. Park, N. Kazantzis, A.G. Parlos, F.P. Vista IV and K.T. Chong Modeling and controllers design of the China CLEAR-IB S. Yan, P. Wang, J. Wan, C. Sun and F. Zhao
19
Reactor Components Combining models of behaviour with operational data to provide enhanced condition monitoring of AGR cores G.M. West, C.J. Wallace and S.D.J. McArthur
11
Thermal Hydraulics Convective heat transfer in a semi-closed BWR-fuel assembly in absence of water S. Schulz, C. Schuster and A. Hurtado Accident analyses for china pressurizer reactor with an innovative conceptual design of passive residual heat removal system M. Wang, D. Zhang, S. Qiu, W. Tian and G. Su Analysis of the horizontal flow in the advanced gas-cooled reactor Y. Duan, S. He, P. Ganesan and J. Gotts Experimental and numerical study of stratification and solidification/melting behaviors G. Li, Y. Oka and M. Furuya Safety and Risk Analysis The predicted effects of selected Phebus FPT1 sump constituents on iodine volatility R.C. Cripps, S. Güntay and B. Jäckel
1
36
45 53 109
99
Special section on the ASTEC severe accident integral code Editorial J.P. Van Dorsselaere, J.M. Bonnet, D. Jacquemain and T. Haste ASTEC V2 severe accident integral code main features, current V2.0 modelling status, perspectives P. Chatelard, N. Reinke, S. Arndt, S. Belon, L. Cantrel, L. Carenini, K. Chevalier-Jabet, F. Cousin, J. Eckel, F. Jacq, C. Marchetto, C. Mun and L. Piar doi:10.1016/S0029-5493(14)00244-1
118
119
Contents/Nuclear Engineering and Design 272 (2014) iv–v
Overview of the independent ASTEC V2.0 validation by SARNET partners P. Chatelard, S. Arndt, B. Atanasova, G. Bandini, A. Bleyer, T. Brähler, M. Buck, I. Kljenak and B. Kujal Validation of ASTEC V2 models for the behaviour of corium in the vessel lower head L. Carénini, J. Fleurot and F. Fichot ASTEC validation on TMI-2 and LOFT LP-FP-2 G. Bandini and F. De Rosa Validation of ASTEC core degradation and containment models P. Kruse, T. Brähler and M.K. Koch Continuous validation of ASTEC containment models and regression testing H. Nowack, N. Reinke and M. Sonnenkalb ASTEC V2 severe accident integral code: Fission product modelling and validation L. Cantrel, F. Cousin, L. Bosland, K. Chevalier-Jabet and C. Marchetto Source term assessment with ASTEC and associated uncertainty analysis using SUNSET tool K. Chevalier-Jabet, F. Cousin, L. Cantrel and C. Séropian ASTEC V2.0 reactor applications on French PWR 900 MWe accident sequences and comparison with MAAP4 V. Lombard, G. Azarian, E. Ducousso and P. Gandrille ASTEC application for in-vessel melt retention modelling in VVER plants Yu.A. Zvonarev, A.M. Volchek, V.L. Kobzar and M.A. Budaev ASTEC investigations of severe core damage behaviour of VVER-1000 in case of loss of coolant accident along with Station-Black-Out P. Groudev, B. Atanasova, B. Chatterjee and Hemant G. Lele ASTEC applications to VVER-440/V213 reactors P. Matejovic, M. Barnak, M. Bachraty and L. Vranka Simulation of the core degradation phase of the Fukushima accidents using the ASTEC code H. Bonneville and A. Luciani ASTEC adaptation for PHWR limited core damage accident analysis P. Majumdar, B. Chatterjee, H.G. Lele, G. Guillard and F. Fichot Assessment on 900-1300 MWe PWRs of the ASTEC-based simulation tool of SGTR thermal-hydraulics for the IRSN Emergency Technical Centre L. Foucher, F. Cousin, J. Fleurot and S. Brethes
v
136 152 163 173 183 195 207 219 224
237 245 261 273
287
Contents lists available at ScienceDirect
Nuclear Engineering and Design journal homepage: www.elsevier.com/locate/nucengdes
CONTENTS Engineering Mechanics Structural integrity assessment of the reactor pressure vessel under the pressurized thermal shock loading M. Chen, F. Lu, R. Wang and A. Ren Material Properties Irradiation embrittlement assessment and prediction of Armenian NPP reactor pressure vessel steels A. Kryukov, G. Sevikyan, V. Petrosyan and A. Vardanyan Models for fuel porosity evolution in UO2 under various regimes of reactor operation V.I. Tarasov and M.S. Veshchunov The oxidation behavior of three different zones of welded Incoloy 800H alloy W.S. Chen, W. Kai, L.W. Tsay and J.J. Kai
84
28 65 92
Reactor Engineering A numerical solution to the point kinetic equations using Taylor-Lie series combined with a scaling and squaring technique H.T. Kim, Y. Park, N. Kazantzis, A.G. Parlos, F.P. Vista IV and K.T. Chong Modeling and controllers design of the China CLEAR-IB S. Yan, P. Wang, J. Wan, C. Sun and F. Zhao
19
Reactor Components Combining models of behaviour with operational data to provide enhanced condition monitoring of AGR cores G.M. West, C.J. Wallace and S.D.J. McArthur
11
Thermal Hydraulics Convective heat transfer in a semi-closed BWR-fuel assembly in absence of water S. Schulz, C. Schuster and A. Hurtado Accident analyses for china pressurizer reactor with an innovative conceptual design of passive residual heat removal system M. Wang, D. Zhang, S. Qiu, W. Tian and G. Su Analysis of the horizontal flow in the advanced gas-cooled reactor Y. Duan, S. He, P. Ganesan and J. Gotts Experimental and numerical study of stratification and solidification/melting behaviors G. Li, Y. Oka and M. Furuya Safety and Risk Analysis The predicted effects of selected Phebus FPT1 sump constituents on iodine volatility R.C. Cripps, S. Güntay and B. Jäckel
1
36
45 53 109
99
Special section on the ASTEC severe accident integral code Editorial J.P. Van Dorsselaere, J.M. Bonnet, D. Jacquemain and T. Haste ASTEC V2 severe accident integral code main features, current V2.0 modelling status, perspectives P. Chatelard, N. Reinke, S. Arndt, S. Belon, L. Cantrel, L. Carenini, K. Chevalier-Jabet, F. Cousin, J. Eckel, F. Jacq, C. Marchetto, C. Mun and L. Piar doi:10.1016/S0029-5493(14)00244-1
118
119
Contents/Nuclear Engineering and Design 272 (2014) iv–v
Overview of the independent ASTEC V2.0 validation by SARNET partners P. Chatelard, S. Arndt, B. Atanasova, G. Bandini, A. Bleyer, T. Brähler, M. Buck, I. Kljenak and B. Kujal Validation of ASTEC V2 models for the behaviour of corium in the vessel lower head L. Carénini, J. Fleurot and F. Fichot ASTEC validation on TMI-2 and LOFT LP-FP-2 G. Bandini and F. De Rosa Validation of ASTEC core degradation and containment models P. Kruse, T. Brähler and M.K. Koch Continuous validation of ASTEC containment models and regression testing H. Nowack, N. Reinke and M. Sonnenkalb ASTEC V2 severe accident integral code: Fission product modelling and validation L. Cantrel, F. Cousin, L. Bosland, K. Chevalier-Jabet and C. Marchetto Source term assessment with ASTEC and associated uncertainty analysis using SUNSET tool K. Chevalier-Jabet, F. Cousin, L. Cantrel and C. Séropian ASTEC V2.0 reactor applications on French PWR 900 MWe accident sequences and comparison with MAAP4 V. Lombard, G. Azarian, E. Ducousso and P. Gandrille ASTEC application for in-vessel melt retention modelling in VVER plants Yu.A. Zvonarev, A.M. Volchek, V.L. Kobzar and M.A. Budaev ASTEC investigations of severe core damage behaviour of VVER-1000 in case of loss of coolant accident along with Station-Black-Out P. Groudev, B. Atanasova, B. Chatterjee and Hemant G. Lele ASTEC applications to VVER-440/V213 reactors P. Matejovic, M. Barnak, M. Bachraty and L. Vranka Simulation of the core degradation phase of the Fukushima accidents using the ASTEC code H. Bonneville and A. Luciani ASTEC adaptation for PHWR limited core damage accident analysis P. Majumdar, B. Chatterjee, H.G. Lele, G. Guillard and F. Fichot Assessment on 900-1300 MWe PWRs of the ASTEC-based simulation tool of SGTR thermal-hydraulics for the IRSN Emergency Technical Centre L. Foucher, F. Cousin, J. Fleurot and S. Brethes
v
136 152 163 173 183 195 207 219 224
237 245 261 273
287