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Author index to volume 88
393
Nuclear Engineering and Design 88 (1985) 393-394 North-Holland, Amsterdam
AUTHOR
INDEX TO VOLUME
Adeli, H. and A.M. Amin, Local effects of impactors on concrete structures Albertini, C., see Eleiche Akimoto, H., Analysis of TKAC-PF1 calculated core heat transfer for a CCTF test Amin, A.M., see Adeli Araj, K.J., see Kroeger Berna, G.A., see Siefken Billone, M.C., see Wazzan Billone, M.C., see Wu Bland, J.G., see Jansky Boyd, R.D., C.P.C. Wong and Y.S. Cha, Thermal-hydraulic assessment of high heat flux removal techniques for fusion applications Brunelli, F., see Cacciabue Cacciabue, P.C., L. Olivi, P. Parisi and F. Brunelli, Assessing the uncertainties in reactor accident consequences by means of RSM: The case of an ATWS in a PWR Cha, Y.S., see Boyd Chawla, T.C. and D.R. Pedersen, A review of modeling concepts for sodium-concrete reactions and a model for liquid sodium transport to the unreacted concrete surface Colman, J., see Kroeger Darbre, G.R. and J.P. Wolf, Nonlinear elastic constitutive law for granular materials applicable to pebble-bed core Eleiche, A.M., C. Albertini and M. Montagnani, The influence of strain-rate history on the ambient tensile strength of AISI type 316 stainless steel Ellingwood, B. and H. Hwang, Probabilistic descriptions of resistance of safety-related structures in nuclear plants Ellison, B., see Hadjian Ercoli, L., P.A.A. Laura, R.O. Grossi and G. Shnchez Sarmiento, Unsteady thermal field in bars of doubly connected cross section with heat generation (Technical note) Erhard, A., see Wi~stenberg
88
88(1985) 301 88(1985) 131 88 (1985) 215 88 (1985) 301 88 (1985) 11 88(1985) 341 88 (1985) 93 88 (1985)195 88(1985) 143
88 (1985)103 88(1985)179
88 (1985)179 88 (1985)103
88(1985) 85 88 (1985) 11
88(1985)161
Fenech, H., Local heat transfer and hot-spot factors in wire-wrap tube bundle Figlhuber, D., In-service inspection experience gained on nuclear steam supply components Grebner, H. and C. Mattheck, Stress intensity factors for complete circumferential surface cracks at the outer wall of a pipe loaded by stress gradients Grossi, R.O., see Ercoli Gupta, A.K. and J.M. Tembulkar, Closure Hadjian, A.H. and B. Ellison, Discussion of the paper: "Dynamic decoupling of secondary systems, by A.K. Gupta and J.M. Tembulkar" Herter, K.-H., see Jansky Hicken, E.F. and K.H. Scholl, Blowdown tests to verify calculation methods for loss-ofcoolant accidents H611er, P., Non-destructive tests on the HDR pressure vessel Hwang, H., see Ellingwood
88(1985) 357
88(1985) 25
88 (1985) 327 88(1985) 377 88(1985) 386
88 (1985)383 88 (1985)143
88(1985)277 88 (1985) 253 88(1985) 169
Ikeda, T., A. Yamanouchi, I. Sumida and M. Naitoh, Dimensionless groups of blowdown experiments Iwano, Y., An efficient numerical method for solving creep problems
88(1985) 333
Jansky, J., K.-H. Herter, J.G. Blauel, D. Munz and H. Stature, Test results and calculations concerning crack propagation under cyclic thermal shock loading on a pressure vessel nozzle
88(1985) 143
88(1985) 49
88 (1985) 131
88(1985)169 88(1985)383
88(1985) 377 88(1985) 35
Katzenmeier, G., see M(tller-Dietsche KOnig, G., Investigations for the verification of calculation methods for earthquake design Kroeger, P.G., J. Colman and K.J. Araj, Thermohydraulics in a high temperature gas-cooled reactor prestressed concrete reactor vessel during unrestricted core heatup accidents Kussmaul, K., Preface
88 (1985) 241
88 (1985) 287
88 (1985) 11 88 (1985) 239
394 Kussmaul, K., Stress and failure studies related to the HDR pressure vessel and piping
Author index
88(1985) 261
Laura, P.A.A., see Ercoli Lee, Y.T. and D. Okrent, Probabilistic costbenefit seismic design criterion for a dedicated shutdown heat removal system
88(1985) 377
Mattheck, C., see Grebner Matthews, J.R., The incorporation of detailed physical models in fuel behaviour codes Meyer-Reumers, H., see Schalk MOller, S.V. and R.Y. Qassim, A resistivity tensor-concept model for three-dimensional fluid flow through rod bundles and the verification of its applicability Montagnani, M., see Eleiche Mt~ller-Dietsche, W. and G. Katzenmeier, Reactor safety research at the large scale facility HDR Munz, D., see Jansky
88(1985) 327
88 (1985) 367
88(1985) 111 88(1985) 229
88 (1985) 1 88 (1985) 131
88 (1985) 241 88 (1985) 143
Nagai, M., S. Shimada, S. Nishimura, H. Ueda and G. Yagawa, Evaluation of SCC crack behavior in zirconium and Zircaloy2 using nonlinear fracture mechanics parameters Naitoh, M., see Ikeda Nakajima, T., FEMAXI-IV: A computer code for the analysis of fuel rod behavior under transient conditions Nishimura, S., see Nagai
88 (1985) 319 88 (1985) 49
Okrent, D., see Wazzan Okrent, D., see Lee Olivi, L., see Cacciabue
88 (1985) 93 88 (1985) 367 88 (1985)179
Parisi, P., see Cacciabue Pedersen, D.R., see Chawla Preumont, A., The generation of non-separable artificial earthquake accelerograms for the design of nuclear power plants
88 (1985) 179 88 (1985) 85
88 (1985) 69 88 (1985) 319
Quassim, R.Y., see M611er
88(1985)
Shnchez Sarmiento, G., see Ercoli Schalk, M., H. Sompek and H. MeyerReumers, Thermal stresses in nonsymmetrically stiffened cylindrical shell; comparison of 2D- and 3D-analysis (Technical note) Scholl, K.H., see Hicken Schulz, E., see Wiastenberg Shah, V.N., see Siefken Shimida, S., see Nagai Siefken, L.J., G.A. Berna and V.N. Shah, FRAP-T6: A computer code for the transient analysis of oxide fuel rods Smith, E., Interpreting the high Kla values obtained in thermal shock tests (Technical note) Sompek, H., see Schalk Stamm, H., see Jansky Sumida, I., see Ikeda
88 (1985) 377
Tatsumi, J., see Wazzan Tembulkar, J.M., see Gupta
88 (1985) 93 88 (1985) 386
Ueda, H., see Nagai
88(1985) 319
Wazzan, A.R., J. Tatsumi, D. Okrent and M.C. Billone, Effect of non-equilibrium fission gas and fuel creep on swelling and release in irradiated carbide fuels Wolf, J.P., see Darbre Wong, C.P.C., see Boyd Wu, S.L. and M.C. Billone, Development and verification of a failure-analysis model for FBR fuel-element cladding Wi'~stenberg, H., E. Schulz and A. Erhard, Fundamental influences on the ultrasonic inspection at cladded nuclear components Yagawa, G., see Nagai Yamanouchi, A., see Ikeda
88 (1985) 59
1
88(1985)229 88 (1985) 277 88 (1985) 35 88 (1985) 341 88 (1985) 319
88 (1985)341
88 (1985)117 88(1985) 229 88 (1985) 143 88 (1985) 49
88(1985) 93 88 (1985) 161 88 (1985)103
88(1985) 195
88(1985) 35 88 (1985) 319 88 (1985) 49
Nuclear Engineering and Design 88 (1985) 393-394 North-Holland, Amsterdam
AUTHOR
INDEX TO VOLUME
Adeli, H. and A.M. Amin, Local effects of impactors on concrete structures Albertini, C., see Eleiche Akimoto, H., Analysis of TKAC-PF1 calculated core heat transfer for a CCTF test Amin, A.M., see Adeli Araj, K.J., see Kroeger Berna, G.A., see Siefken Billone, M.C., see Wazzan Billone, M.C., see Wu Bland, J.G., see Jansky Boyd, R.D., C.P.C. Wong and Y.S. Cha, Thermal-hydraulic assessment of high heat flux removal techniques for fusion applications Brunelli, F., see Cacciabue Cacciabue, P.C., L. Olivi, P. Parisi and F. Brunelli, Assessing the uncertainties in reactor accident consequences by means of RSM: The case of an ATWS in a PWR Cha, Y.S., see Boyd Chawla, T.C. and D.R. Pedersen, A review of modeling concepts for sodium-concrete reactions and a model for liquid sodium transport to the unreacted concrete surface Colman, J., see Kroeger Darbre, G.R. and J.P. Wolf, Nonlinear elastic constitutive law for granular materials applicable to pebble-bed core Eleiche, A.M., C. Albertini and M. Montagnani, The influence of strain-rate history on the ambient tensile strength of AISI type 316 stainless steel Ellingwood, B. and H. Hwang, Probabilistic descriptions of resistance of safety-related structures in nuclear plants Ellison, B., see Hadjian Ercoli, L., P.A.A. Laura, R.O. Grossi and G. Shnchez Sarmiento, Unsteady thermal field in bars of doubly connected cross section with heat generation (Technical note) Erhard, A., see Wi~stenberg
88
88(1985) 301 88(1985) 131 88 (1985) 215 88 (1985) 301 88 (1985) 11 88(1985) 341 88 (1985) 93 88 (1985)195 88(1985) 143
88 (1985)103 88(1985)179
88 (1985)179 88 (1985)103
88(1985) 85 88 (1985) 11
88(1985)161
Fenech, H., Local heat transfer and hot-spot factors in wire-wrap tube bundle Figlhuber, D., In-service inspection experience gained on nuclear steam supply components Grebner, H. and C. Mattheck, Stress intensity factors for complete circumferential surface cracks at the outer wall of a pipe loaded by stress gradients Grossi, R.O., see Ercoli Gupta, A.K. and J.M. Tembulkar, Closure Hadjian, A.H. and B. Ellison, Discussion of the paper: "Dynamic decoupling of secondary systems, by A.K. Gupta and J.M. Tembulkar" Herter, K.-H., see Jansky Hicken, E.F. and K.H. Scholl, Blowdown tests to verify calculation methods for loss-ofcoolant accidents H611er, P., Non-destructive tests on the HDR pressure vessel Hwang, H., see Ellingwood
88(1985) 357
88(1985) 25
88 (1985) 327 88(1985) 377 88(1985) 386
88 (1985)383 88 (1985)143
88(1985)277 88 (1985) 253 88(1985) 169
Ikeda, T., A. Yamanouchi, I. Sumida and M. Naitoh, Dimensionless groups of blowdown experiments Iwano, Y., An efficient numerical method for solving creep problems
88(1985) 333
Jansky, J., K.-H. Herter, J.G. Blauel, D. Munz and H. Stature, Test results and calculations concerning crack propagation under cyclic thermal shock loading on a pressure vessel nozzle
88(1985) 143
88(1985) 49
88 (1985) 131
88(1985)169 88(1985)383
88(1985) 377 88(1985) 35
Katzenmeier, G., see M(tller-Dietsche KOnig, G., Investigations for the verification of calculation methods for earthquake design Kroeger, P.G., J. Colman and K.J. Araj, Thermohydraulics in a high temperature gas-cooled reactor prestressed concrete reactor vessel during unrestricted core heatup accidents Kussmaul, K., Preface
88 (1985) 241
88 (1985) 287
88 (1985) 11 88 (1985) 239
394 Kussmaul, K., Stress and failure studies related to the HDR pressure vessel and piping
Author index
88(1985) 261
Laura, P.A.A., see Ercoli Lee, Y.T. and D. Okrent, Probabilistic costbenefit seismic design criterion for a dedicated shutdown heat removal system
88(1985) 377
Mattheck, C., see Grebner Matthews, J.R., The incorporation of detailed physical models in fuel behaviour codes Meyer-Reumers, H., see Schalk MOller, S.V. and R.Y. Qassim, A resistivity tensor-concept model for three-dimensional fluid flow through rod bundles and the verification of its applicability Montagnani, M., see Eleiche Mt~ller-Dietsche, W. and G. Katzenmeier, Reactor safety research at the large scale facility HDR Munz, D., see Jansky
88(1985) 327
88 (1985) 367
88(1985) 111 88(1985) 229
88 (1985) 1 88 (1985) 131
88 (1985) 241 88 (1985) 143
Nagai, M., S. Shimada, S. Nishimura, H. Ueda and G. Yagawa, Evaluation of SCC crack behavior in zirconium and Zircaloy2 using nonlinear fracture mechanics parameters Naitoh, M., see Ikeda Nakajima, T., FEMAXI-IV: A computer code for the analysis of fuel rod behavior under transient conditions Nishimura, S., see Nagai
88 (1985) 319 88 (1985) 49
Okrent, D., see Wazzan Okrent, D., see Lee Olivi, L., see Cacciabue
88 (1985) 93 88 (1985) 367 88 (1985)179
Parisi, P., see Cacciabue Pedersen, D.R., see Chawla Preumont, A., The generation of non-separable artificial earthquake accelerograms for the design of nuclear power plants
88 (1985) 179 88 (1985) 85
88 (1985) 69 88 (1985) 319
Quassim, R.Y., see M611er
88(1985)
Shnchez Sarmiento, G., see Ercoli Schalk, M., H. Sompek and H. MeyerReumers, Thermal stresses in nonsymmetrically stiffened cylindrical shell; comparison of 2D- and 3D-analysis (Technical note) Scholl, K.H., see Hicken Schulz, E., see Wiastenberg Shah, V.N., see Siefken Shimida, S., see Nagai Siefken, L.J., G.A. Berna and V.N. Shah, FRAP-T6: A computer code for the transient analysis of oxide fuel rods Smith, E., Interpreting the high Kla values obtained in thermal shock tests (Technical note) Sompek, H., see Schalk Stamm, H., see Jansky Sumida, I., see Ikeda
88 (1985) 377
Tatsumi, J., see Wazzan Tembulkar, J.M., see Gupta
88 (1985) 93 88 (1985) 386
Ueda, H., see Nagai
88(1985) 319
Wazzan, A.R., J. Tatsumi, D. Okrent and M.C. Billone, Effect of non-equilibrium fission gas and fuel creep on swelling and release in irradiated carbide fuels Wolf, J.P., see Darbre Wong, C.P.C., see Boyd Wu, S.L. and M.C. Billone, Development and verification of a failure-analysis model for FBR fuel-element cladding Wi'~stenberg, H., E. Schulz and A. Erhard, Fundamental influences on the ultrasonic inspection at cladded nuclear components Yagawa, G., see Nagai Yamanouchi, A., see Ikeda
88 (1985) 59
1
88(1985)229 88 (1985) 277 88 (1985) 35 88 (1985) 341 88 (1985) 319
88 (1985)341
88 (1985)117 88(1985) 229 88 (1985) 143 88 (1985) 49
88(1985) 93 88 (1985) 161 88 (1985)103
88(1985) 195
88(1985) 35 88 (1985) 319 88 (1985) 49