Nuclear Engineering and Design Nuclear Engineering and Design 168 (1997) 375—376 Author Index of Volume 168 Alberman, A., M. Roche, P. Couffin, S. Ben- France from the in-service inspection re- dotti, D.J. Moulin and J.L. Boutfroy, sults 168 (1996) 255 Technique for power ramp tests in the Coudray, R., M. Eid and G.L. Fiorini, A ISABELLE | loop of the OSIRIS reactor 168 (1996) 293 differential model for equivalent parame- Asou, M. and J. Porta, Prospects for poison- ters: Application to two residual heat re- ing reactor cores of the future 168 (1996) 261 moval systems parameterization and interpretation of results 168 (1996) 227 Baetslé, L.H. and C. De Raedt, Limitations Couffin, P., see Alberman, A. 168 (1996) 293 of actinide recycle and fuel cycle conse- quences: a global analysis : Part 1: Global De Raedt, C., see Baetslé, L.H. 168 (1996) 191 fuel cycle analysis 168 (1996) 191 De Raedt, C., see Baetslé, L.H. 168 (1996) 203 Baetslé, L.H. and C. De Raedt, Limitations Devillers-Guerville, L., J. Besson and A. of actinide recycle and fuel cycle conse- Pineau, Notch fracture toughness of a cast quences. A global analysis : Part 2: Recy- duplex stainless steel: modelling of experi- mental scatter and size effect 168 (1996) 211 cle of actinides in thermal reactors: impact Duijvestijn, G., see Brosi, S. 168 (1996) 77 of high burn up LWR-UO, fuel irradiation and multiple recycle of LWR-MOX fuel Eid, M., see Coudray, R. 168 (1996) 227 on the radiotoxic inventory 168 (19962)0 3 Bendotti, S., see Alberman, A. 168 (19962)9 3 Fiorini, G.L., see Coudray, R. 168 (1996) 227 Bengtsson, S., see Grounes, M. 168 (19961)5 1 Berger, H.-D., see BOhme, R. 168 (19962)7 1 Garat, C. and C.-Y. Rieg, Validation of neu- Besson, J., see Devillers-Guerville, L. 168 (19962)1 1 tron propagation calculations using the Blind, D., see Kussmaul, K. 168 (1996) 53 DORT and DOTSYN codes and the spe- Bohme, R., H.-D. Berger, R. Chawla, H. cial dosimetry benchmark experiment at Hager, R. Seiler and T. Williams, Void the French St. Laurent reactor 168 (1996) 281 coefficient analysis of an LWR lattice ex- Gomez Briceno, M.D., see Navas, M. 168 (1996) 183 periment with high-enrichment MOX fuel 168 (1996) 271 Graslund, C., see Grounes, M. 168 (1996) 177 Boutfroy, J.L., see Alberman, A. 168 (1996) 293 Graslund, C., see Grounes, M. 168 (1996) 167 Brosi, S., G. Duijvestijin, H. Hirschmann, Graves III, H.L., see Rodriguez, M. 168 (1996) 23 B.S. Jackel, K. Nakada, J.A. Patorski, R. Grounes, M., C. Graslund, G. Lysell and H. Résel, H.P. Seifert and P. Tipping, Tomani, Fuel R&D at Studsvik: III. Stud- CORVIS. Investigation of light water reac- ies of special phenomena in fuel behaviour: tor lower head failure modes 168 (1996) 77 lift-off and defect fuel degradation 168 (1996) Brimmer, G., see Wachter, O. 168 (1996) 35 Grounes, M., C. Graslund, M. Carlsson and T. Unger, Fuel R&D at Studsvik: [V. Up- Carlsson, M., see Grounes, M. 168 (1996) 177 coming international fuel R&D projects 168 (1996) Carlsson, M., see Grounes, M. 168 (1996) 129 Grounes, M., G. Lysell and S. Bengtsson, Cattant, F., Lessons learned from the exami- Fuel R&D at Studsvik: II. General studies nation of tubes pulled from Electricité de of fuel behaviour including pellet-cladding France steam generators 168 (1996) 241 interaction 168 (1996) Chawla, R., see BoOhme, R. 168 (1996) 271 Grounes, M., H. Tomani, A. Lassing and M. Comby, R., Secondary side corrosion in Carlsson, Fuel R&D at Studsvik: I. Intro- steam generator tubes: lessons learned in duction and experimental facilities 168 (1996) 376 Author Index Nuclear Engineering and Design 168 (1997) 375-376 Hager, H., see Bohme, R. 168 (1996) 271 Nakada, K., see Brosi, S. 168 (1996) 77 Helton, J.C. and K.M. Trauth, Comments Nakamura, J., see Hidaka, A. 168 (1996) 361 on an evaluation of the 1992 performance Navas, M. and M.D. Gomez Bricefio, Be- assessment for the Waste Isolation Pilot haviour of reference electrodes in the mon- Plant 168 (1996) 3: itoring of corrosion potential at high Hidaka, A., J. Nakamura and J. Sugimoto, temperature 168 (1996) 183 Influence of thermal properties of zirconia Nhim, K., see Zarrabi, K. 168 (1996) 313 shroud on analysis of PHEBUS FPT0O bundle degradation test with ICARE2 Patorski, J.A., see Brosi, S. 168 (1996) 77 code 168 (1996) Pineau, A., see Devillers-Guerville, L. 168 (1996) 211 Hirschmann, H., see Brosi, S. 168 (1996) Popescu, I.A., see Horhoianu, G. 168 (1996) 319 Horhoianu, G., D.R. Moscalu and IA. Porta, J., see Asou, M. 168 (1996) 261 Popescu, Strain and stress analysis in the Rahman, S., G. Wilkowski and R. Mohan, end-cap weld region of a fuel element 168 (1996) 319 Horie, T., see Takeda, T. 168 (1996) 11 Low-cycle fatigue crack growth consider- Huizhong, Z., The uranium—zirconium hy- ations in pipe fracture analyses 168 (1996) 105 dride pulsed reactor and its use in science Rieg, C.-Y., see Garat, C. 168 (1996) 281 Roche, M., see Alberman, A. 168 (1996) 293 and technology 168 (1996) Rodriguez, M., Y.-G. Zhang, D. Lotez, H.L. Graves III and R.E. Klingner, Dynamic Iwata, K., see Takeda, T. 168 (1996) behaviour of anchors in cracked and un- cracked concrete: a progress report 168 (1996) Jackel, B.S., see Brosi, S. 168 (1996) Rosel, R., see Brosi, S. 168 (1996) Jirsa, P., Monitoring of the VVER nuclear reactor internals 168 (1996) Seifert, H.P., see Brosi, S. 168 (1996) Seiler, R., see BOhme, R. 168 (1996) 271 Khabensky, V.B., S.D. Malkin, V.V. Shalia, Shalia, V.V., see Khabensky, V.B. 168 (1996) 119 Z.-Y. Wang, G.-H. Wang and E. Lin, Sugimoto, J., see Hidaka, A. 168 (1996) 361 Comparative analysis of RBMK_ core channel void fraction determined by RE- Takeda, T., K. Kunitomi, T. Horie and K. LAPS, KOBRA, and a new drift flux cor- Iwata, Feasibility study on the applicabil- relation 168 (1996) ity of a diffusion-welded compact interme- Klingner, R.E., see Rodriguez, M. 168 (1996) diate heat exchanger to next-generation Kunitomi, K., see Takeda, T. 168 (1996) high temperature gas-cooled reactor 168 (1996) 11 Kussmaul, K., D. Blind and V. Lapple, New Tipping, P., see Brosi, S. 168 (1996) 77 observations on the crack growth rate of Tomani, H., see Grounes, M. 168 (1996) 167 low alloy nuclear grade ferritic steels under Tomani, H., see Grounes, M. 168 (1996) 129 constant active load in oxygenated high- Trauth, K.M., see Helton, J.C. 168 (1996) 339 temperature water 168 (1996) Unger, T., see Grounes, M. 168 (1996) 177 Lapple, V., see Kussmaul, K. 168 (1996) Lassing, A., see Grounes, M. 168 (1996) Wachter, O. and G. Briimmer, Experiences Lee, W.W.-L., A critical evaluation of the with austenitic steels in boiling water reac- 1992 performance assessment for the tors 168 (1996) 35 Waste Isolation Pilot Plant 168 (1996) 325 Wang, G.-H., see Khabensky, V.B. 168 (1996) 119 Lin, E., see Khabensky, V.B. 168 (1996) Wang, Z.-Y., see Khabensky, V.B. 168 (1996) 119 Lotez, D., see Rodriguez, M. 168 (1996) Wilkowski, G., see Rahman, S. 168 (1996) 105 Lysell, G., see Grounes, M. 168 (1996) Williams, T., see BOhme, R. 168 (1996) 271 Lysell, G., see Grounes, M. 168 (1996) Zarrabi, K., H. Zhang and K. Nhim, Plastic Malkin, S.D., see Khabensky, V.B. 168 (1996) collapse pressure of cylindrical vessels con- Mohan, R., see Rahman, S. 168 (1996) taining longitudinal surface cracks 168 (1996) 313 Moscalu, D.R., see Horhoianu, G. 168 (1996) 319 Zhang, H., see Zarrabi, K. 168 (1996) 313 Moulin, D.J., see Alberman, A. 168 (1996) 293 Zhang, Y.-G., see Rodriguez, M. 168 (1996) 23 Nuclear Engineering oe 2 . and Design ELSEVIER Nuclear Engineering and Design 168 (1997) 377-378 Subject Index of Volume 168 Engineering mechanics K. Zarrabi, H. Zhang, K. Nhim 168 (1997) 313 Strain and stress analysisin theend-cap weld New observations on the crack growth rate region of a fuel element of low alloy nuclear grade ferritic steels G. Horhoianu, D.R. Moscalu, under constant active load in oxygenated L.A. Popescu 168 (1997) 319 high-temperature water K. Kussmaul, D. Blind, V. Lapple 168 (1997) 53 Mechanical design, component fabrication and testing Plastic collapse pressure of cylindrical ves- sels containing longitudinal surface Monitoring of the VVER nuclear reactor cracks internals K. Zarrabi, H. Zhang, K. Nhim 168 (1997) 313 P. Jirsa 168 (1997) Strainand stress analysisintheend-cwaepl d Feasibility study on the applicability of a region of a fuel element diffusion-welded compact intermediate G. Horhoianu, D.R. Moscalu, heat exchanger to next-generation high 1.A. Popescu 168 (1997) 319 temperature gas-cooled reactor T. Takeda, K. Kunitomi, T. Horie, Materials properties K. Iwata 168 (1997) New observations on the crack growth rate Dynamic behaviour of anchors in cracked of low alloy nuclear grade ferritic steels and uncracked concrete: a progressreport under constant active load in oxygenated M. Rodriguez, Y-G. Zhang, D. Lotez, H.L. high-temperature water Graves III, R.E. Klingner 168 (1997) K. Kussmaul, D. Blind, V. Lapple 168 (1997) 53 Experiences with austenitic steels in boiling Limiofatctinaide treciycleo andn fueslcy cle water reactors consequences: a global analysis. Part 1: O. Wachter, G. Briimmer 168 (1997) Global fuel cycle analysis CORVIS. Investigation ofl ight water reac- L.H. Baetslé, Ch. De Raedt 168 (1997) 191 tor lower head failure modes Notch fracture toughness of a cast duplex S. Borsi, G. Duijvsetijn, H. Hirschmann, stainless steel: modelling of experimental scatter and size effect B.S. Jackel, K. Nakada, J.A. Patorski, L. Devillers-Guerville, J. Besson, R. Rosel, H.P. Seifert, Ph. Tipping 168 (1997) A. Pineau 168 (1997) Low-cycle fatigue crack growth condisera- Lessons learned from the examination of tions in pipe fracture analyses tubes pulled from Electricité de France S. Rahman, G. Wilkowski, R. Mohan 168 (1997) 105 steam generators Compaanalyrsis aoft RBMiK cvoree ch an- F. Cattant 168 (1997) 241 nel void fraction determined by RELAPS, Secondary | side corrosion in steam KOBRA, and a new drift flux correlation generator tubes: lessons learned in France V.B. Khabensky, S.D. Malkin, V.V. Shalia, from the in-services inspection results Z.-Y. Wang, G.-H. Wang, E. Lin 168 (1997) 119 R. Comby 168 (1997) 255 A critical evaluation of the 1992 perfor- Plastic collapse pressure of cylindrical ves- mance assessment for the Waste Isolation sels containing longitudinal surface Pilot Plant cracks W. W.-L. Lee 168 (1997) 325 378 Subject Index Nuclear Engineering and Design 168 (1997) 377-378 Comments on an evaluation of the 1992 special phenomena in fuel behaviour: performance assessment for the Waste lift-off and defect fuel degradation Isolation Pilot Plant M. Grounes, C. Griaslund, G. Lysel, H. J.C. Helton, K.M. Trauth 168 (1997) 339 Tomani 168 (1997) 167 Influence of thermal properties of zirco- Fuel R&D at Studsvik. IV. Upcoming nia shroud on analysis of PHEBUS international fuel R&D projects FPTO bundle degradation test with M. Grounes, C. Graslund, M. Carlsson, ICARE2 code T. Unger 168 (1997) 177 A. Hidaka, J. Nakamura, J. Sugimoto 168 (1997) 361 Prospects for poisoning reactor cores of the future Layout of nuclear facilities M. Asou, J. Porta 168 (1997) 261 Void coefficient analysis of an LWR lat- The uranium-zirconium hydride pulsed tice experiment with high-enrichment reactor and its use in science and tech- MOX fuel nology R. Bohme, H.-D. Berger, R. Chawla, H. Z. Hiuzhong 168 (1997) 305 Hager, R. Seiler, T. Williams 168 (1997) 271 Validation of neutron propagation calcu- Discussion lations using the DORT and DOTSYN codes and the special dosimetry bench- Limitations of actinide recycle and fuel mark experiment at the French St. cycle consequences. A global analysis. Laurent reactor Part 2: Recycles of actinides in thermal C. Garat, C.-Y. Rieg 168 (1997) 281 reactors: impact of high burn up LWR- Technique for pwer ramp tests in the UO, fuel irradiation and multiple recy- ISABELLE | loop of the OSIRIS reac- cles of LWR-MOX fuel on the tor radiotoxic inventory A. Alberman, M. Roche, P. Couffin, S. L.H. Baetslé, Ch. De Raedt 168 (1997) 203 Bendotti, D.J. Moulin, J.L. Boutfroy 168 (1997) 293 Core physics and fuel design Nuclear safety Fuel R&D at Studsvik. I. Introduction Behaviour of reference electrodes in the and experimental facilites monitoring of corrosion potential at M. Grounes, H. Tomani, A. Lassing, M. high temperature Carlsson 168 (1997) 129 M. Navas, M.D. Gomez Bricéno 168 (1997) 183 Fuel R&D at Studsvik. II. General stud- A differential model for equivalent ies of fuel behaviour including pellet- parameters. Application to two resid- cladding interaction ual heat temoval systems parameteriza- M. Grounes, G. Lysell, S. Bengtsson 168 (1997) 151 tion and interpretation of results Fuel R&D at Studsvik. III. Studies of R. Coudray, M. Eid, G.L. Fiorini 168 (1997) 227