Table Of Content

Nuclear Engineering and Design 143 (1993) 315-316 315 North-Holland Author Index to Volume 143 Ahmad, J., see Brust, F.W. 143 (1993) 201 Haldar, S.C., see Mohanty, A.K. 143 (1993) 83 Aksan, S.N., F. Stierli and G.Th. Analytis, Harrod, D.L., see Middlebrooks, W.B. 143 (1993) 159 Boil-off experiments with the PSI- Hernalsteen, P., PWSCC in the tube expan- NEPTUN facility: Analysis and code as- sion zone — an overview 143 (1993) 131 sessment overview report 143 (1993) 245 Hsu-Wen Chiang, and S. C.A. Jones, Simu- Analytis, G.Th., see Aksan, S.N. 143 (1993) 245 lating the mixing of helium and air by mixing salt water and fresh water in a scaled enclosure 143 (1993) 55 Brauer, G. and F. Eichhorn, Considerations about irradiation-induced precipitates in Soviet type reactor pressure vessel steels 143 (1993) 301 Igusa, T., R. Sinha, E. Kokubo, S.-I. Fu- Brickstad, B., see Brust, F.W. 143 (1993) 201 rukawa and J.-I. Kawahata, Analysis of piping with hysteretic supports using re- Brocks, W., W. Miller, H.-D. Noack and H. sponse spectra 143 (1993) 187 Veith, Fracture mechanics investigations Ishii, M., see No, H.C. 143 (1993) 265 on a pipe with a circumferential flaw supported by FEM 143 (1993) 171 Brust, F.W., J. Ahmad, B. Brickstad, C. Faidy Jones, R.L., J.D. Gilman and J.L. Nelson, Controlling stress corrosion cracking in and P. Gilles, Comparisons between fi- Boiling Water Reactors 143 (1993) 111 nite-element analysis predictions and pipe fracture experiments 143 (1993) 201 Kawahata, J.-I., see Igusa, T. 143 (1993) 187 Kokubo, E., see Igusa, T. 143 (1993) 187 C.A. Jones, S., see Hsu-Wen Chiang, 143 (1993) 55 Chi-Hung Hwang, , see Wang, W.-C. 143 (1993) 217 Lee, J.B. and J.H. Song, A study on the Cinotti, L. and F.L. Rizzo, The Inherently behavior of a crack located at the striping Safe Immersed System (ISIS) reactor 143 (1993) 295 zone in a thermally stratified pipe 143 (1993) 229 Li, H., see Wang, D. 143 (1993) 9 D’Auria, F., see Petrangeli, G. 143 (1993) 25 Lin, J., see Wang, D. 143 (1993) 9 Dong, D., see Wang, D. 143 (1993) 9 Mavko, B., A. Stritar and A. ProSek, Appli- Eichhorn, F., see Brauer, G. 143 (1993) 301 cation of code scaling, applicability and Eto, M., see Oku, T. 143 (1993) 239 uncertainty methodology to large break LOCA analysis of two loop PWR 143 (1993) 95 Mazzini, M., see Petrangeli, G. 143 (1993) 25 Faidy, C., see Brust, F.W. 143 (1993) 201 Middlebrooks, W.B., D.L. Harrod and R.E. Furukawa, S.-I., see Igusa, T. 143 (1993) 187 Gold, Residual stresses associated with the hydraulic expansion of steam genera- Gao, Z., see Wang, D. 143 (1993) 1 tor tubing into tubesheets 143 (1993) 159 Gao, Z., see Wang, D. 143 (1993) 9 Mohanty, A.K., S.C. Haldar and S. Sen- Garud, Y.S. and K.E. Watkins, 3D gupta, Low Reynolds number flow and stress /deflection analysis of tubesheet heat transfer experiments in 7-rod verti- and U-tubes 143 (1993) 151 cal bundles 143 (1993) 83 Garud, Y.S., Service stresses in expansion Miller, W., see Brocks, W. 143 (1993) 171 transitions of heat-exchanger U-tube joints 143 (1993) 143 Nelson, J.L., see Jones, R.L. 143 (1993) 111 Gilles, P., see Brust, F.W. 143 (1993) 201 Neymotin, L.Y., see Rohatgi, U.S. 143 (1993) 69 Gilman, J.D., see Jones, R.L. 143 (1993) 111 No, H.C. and M. Ishii, Scaling study of in- Gold, R.E., see Middlebrooks, W.B. 143 (1993) 159 core boil-off and heating process 143 (1993) 265 316 Author Index to Volume 143 Noack, H.-D., see Brocks, W. 143 (1993) 171 Veith, H., see Brocks, W. 143 (1993) 171 Oku, T. and M. Eto, Relation between static Wang, D., D. Zhang, D. Dong, Z. Gao, H. and dynamic Young’s modulus of nuclear Li, J. Lin and Q. Su, Experimental study graphites and carbon 143 (1993) 239 and operation experiences of the 5 MW Nuclear Heating Reactor 143 (1993) 9 Petrangeli, G., R. Tononi, F. D’Auria and Wang, D., Z. Gao and W. Zheng, Technical M. Mazzini, The SSN: an emergency sys- design features and safety analysis of the tem based on intentional coolant depres- 200 MWt Nuclear Heating Reactor 143 (1993) 1 surization for PWRs 143 (1993) 25 Wang, D., The design characteristics and ProSek, A., see Mavko, B. 143 (1993) 95 construction experiences of the 5 MWt Nuclear Heating Reactor 143 (1993) 19 Rizzo, F.L., see Cinotti, L. 143 (1993) 295 Wang, W.-C., Tsai-Lin Chen and Chi- Rohatgi, U.S., L.Y. Neymotin and W. Wulff, Hung Hwang, Transient thermal stress Assessment of RAMONA-3B methodol- intensity factors of edge-cracked semi-in- ogy with oscillatory flow tests 143 (1993) 69 finite plates 143 (19932)1 7 Watkins, K.E., see Garud, Y.S. 143 (1993) 151 Sengupta, S., see Mohanty, A.K. 143 (1993) 83 Wulff, W., see Rohatgi, U.S. 143 (1993) 69 Sinha, R., see Igusa, T. 143 (19931)8 7 Song, J.H., see Lee, J.B. 143 (19932)2 9 Yanagisawa, K., Behaviour of small-sized Stierli, F., see Aksan, S.N. 143 (19932)4 5 BWR fuel under reactivity initiated acci- Stritar, A., see Mavko, B. 143 (1993) 95 dent conditions in comparison with stan- Su, Q., see Wang, D. 143 (1993) 9 dard BWR fuel 143 (1993) 285 Tononi, R., see Petrangeli, G. 143 (1993) 25 Zhang, D., see Wang, D. 143 (1993) 9 Tsai-Lin Chen, , see Wang, W.-C. 143 (1993) 217 Zheng, W., see Wang, D. 143 (1993) 1 Nuclear Engineering and Design 143 (1993) 317-318 317 North-Holland Subject Index to Volume 143 Analysis of piping with hysteretic supports Thermal and fluid design using response spectra, T. Igusa, R. Sinha, E. Kokubo, S.-I. Furukawa and The SSN: an emergency system based on J.-1. Kawahata 143 (1993) 187 Comparisons between finite-element analy- intentional coolant depressurization for sis predictions and pipe fracture experi- PWRs, G. Petrangeli, R. Tononi, F. D’Auria and M. Mazzini 143 (1993) 25 ments, F.W. Brust, J. Ahmad, B. Brick- Simulating the mixing of helium and air by stad, C. Faidy and P. Gilles 143 (1993) 201 Transient thermal stress intensity factors of mixing salt water and fresh water in a edge-cracked semi-infinite plates, W.-C. scaled enclosure, Hsu-Wen Chiang and S. C.A. Jones 143 (1993) 55 Wang, Tsai-Lin Chen and Chi-Hung Assessment of RAMONA-3B methodology Hwang 143 (19932)1 7 with oscillatory flow tests, U.S. Rohatgi, Relation between static and dynamic L.Y. Neymotin and W. Wulff 143 (1993) 69 Young’s modulus of nuclear graphites and carbon, T. Oku and M. Eto 143 (1993) 239 Low Reynolds number flow and heat trans- fer experiments in 7-rod vertical bundles, A.K. Mohanty, S.C. Haldar and S. Sen- Materials properties gupta 143 (1993) 83 Application of code scaling, applicability and Relation between static and dynamic uncertainty methodology to large break Young’s modulus of nuclear graphites LOCA analysis of two loop PWR, B. and carbon, T. Oku and M. Eto 143 (19932)3 9 Mavko, A. Stritar and A. ProSek 143 (1993) 95 Considerations about irradiation-induced Boil-off experiments with the PSI-NEPTUN precipitates in Soviet type reactor pres- facility: Analysis and code assessment sure vessel steels, G. Brauer and F. Eich- overview report, S.N. Aksan, F. Stierli horn 143 (19933)0 1 and G.Th. Analytis 143 (1993) 245 Scaling study of in-core boil-off and heating Mechanical design, component fabrication and testing process, H.C. No and M. Ishii 143 (1993) 265 Fracture mechanics investigations on a pipe Engineering mechanics with a circumferential flaw supported by FEM, W. Brocks, W. Miller, H.-D. Controlling stress corrosion cracking in Boil- Noack and H. Veith 143 (1993) 171 ing Water Reactors, R.L. Jones, J.D. Comparisons between finite-element analy- Gilman and J.L. Nelson 143 (1993) 111 sis predictions and pipe fracture experi- Service stresses in expansion transitions of ments, F.W. Brust, J. Ahmad, B. Brick- heat-exchanger U-tube joints, Y.S. Garud 143 (1993) 143 stad, C. Faidy and P. Gilles 143 (1993) 201 3D stress /deflection analysis of tubesheet and U-tubes, Y.S. Garud and K.E. Watkins 143 (1993) 151 Reactor concepts and systems analysis Residual stresses associated with the hy- draulic expansion of steam generator tub- Technical design features and safety analysis ing into tubesheets, W.B. Middlebrooks, of the 200 MWt Nuclear Heating Reac- D.L. Harrod and R.E. Gold 143 (1993) 159 tor, D. Wang, Z. Gao and W. Zheng 143 (1993) 1 Fracture mechanics investigations on a pipe Experimental study and operation experi- with a circumferential flaw supported by ences of the 5 MW Nuclear Heating Re- FEM, W. Brocks, W. Miiller, H.-D. actor, D. Wang, D. Zhang, D. Dong, Z. Noack and H. Veith 143 (1993) 171 Gao, H. Li, J. Lin and Q. Su 143 (1993) 9 318 Subject Index to Volume 143 The design characteristics and construction Nuclear safety experiences of the 5 MWt Nuclear Heat- ing Reactor, D. Wang 143 (1993) 19 The SSN: an emergency system based on PWSCC in the tube expansion zone — an intentional coolant depressurization for overview, P. Hernalsteen 143 (1993) 131 PWRs, G. Petrangeli, R. Tononi, F. The Inherently Safe Immersed System (ISIS) D’Auria and M. Mazzini 143 (1993) 25 reactor, L. Cinotti and F.L. Rizzo 143 (1993) 295 Simulating the mixing of helium and air by mixing salt water and fresh water in a Safeguard engineering scaled enclosure, Hsu-Wen Chiang and S. C.A. Jones 143 (1993) 55 Controlling stress corrosion cracking in Boil- Assessment of RAMONA-3B methodology ing Water Reactors, R.L. Jones, J.D. with oscillatory flow tests, U.S. Rohatgi, Gilman and J.L. Nelson 143 (1993) 111 L.Y. Neymotin and W. Wulff 143 (1993) 69 Application of code scaling, applicability and Layout of nuclear facilities uncertainty methodology to large break LOCA analysis of two loop PWR, B. The Inherently Safe Immersed System (ISIS) Mavko, A. Stritar and A. ProSek 143 (1993) 95 reactor, L. Cinotti and F.L. Rizzo 143 (1993) 295 Boil-off experiments with the PSI-NEPTUN facility: Analysis and code assessment Core physics and fuel design overview report, S.N. Aksan, F. Stierli and G.Th. Analytis 143 (1993) 245 Behaviour of small-sized BWR fuel under reactivity initiated accident conditions in comparison with standard BWR fuel, K. Yanagisawa 143 (1993) 285

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Nuclear Engineering and Design 143 (1993) 315-316 315 North-Holland Author Index to Volume 143 Ahmad, J., see Brust, F.W. 143 (1993) 201 Haldar, S.C., see Mohanty, A.K. 143 (1993) 83 Aksan, S.N., F. Stierli and G.Th. Analytis, Harrod, D.L., see Middlebrooks, W.B. 143 (1993) 159 Boil-off experiments with the PSI- Hernalsteen, P., PWSCC in the tube expan- NEPTUN facility: Analysis and code as- sion zone — an overview 143 (1993) 131 sessment overview report 143 (1993) 245 Hsu-Wen Chiang, and S. C.A. Jones, Simu- Analytis, G.Th., see Aksan, S.N. 143 (1993) 245 lating the mixing of helium and air by mixing salt water and fresh water in a scaled enclosure 143 (1993) 55 Brauer, G. and F. Eichhorn, Considerations about irradiation-induced precipitates in Soviet type reactor pressure vessel steels 143 (1993) 301 Igusa, T., R. Sinha, E. Kokubo, S.-I. Fu- Brickstad, B., see Brust, F.W. 143 (1993) 201 rukawa and J.-I. Kawahata, Analysis of piping with hysteretic supports using re- Brocks, W., W. Miller, H.-D. Noack and H. sponse spectra 143 (1993) 187 Veith, Fracture mechanics investigations Ishii, M., see No, H.C. 143 (1993) 265 on a pipe with a circumferential flaw supported by FEM 143 (1993) 171 Brust, F.W., J. Ahmad, B. Brickstad, C. Faidy Jones, R.L., J.D. Gilman and J.L. Nelson, Controlling stress corrosion cracking in and P. Gilles, Comparisons between fi- Boiling Water Reactors 143 (1993) 111 nite-element analysis predictions and pipe fracture experiments 143 (1993) 201 Kawahata, J.-I., see Igusa, T. 143 (1993) 187 Kokubo, E., see Igusa, T. 143 (1993) 187 C.A. Jones, S., see Hsu-Wen Chiang, 143 (1993) 55 Chi-Hung Hwang, , see Wang, W.-C. 143 (1993) 217 Lee, J.B. and J.H. Song, A study on the Cinotti, L. and F.L. Rizzo, The Inherently behavior of a crack located at the striping Safe Immersed System (ISIS) reactor 143 (1993) 295 zone in a thermally stratified pipe 143 (1993) 229 Li, H., see Wang, D. 143 (1993) 9 D’Auria, F., see Petrangeli, G. 143 (1993) 25 Lin, J., see Wang, D. 143 (1993) 9 Dong, D., see Wang, D. 143 (1993) 9 Mavko, B., A. Stritar and A. ProSek, Appli- Eichhorn, F., see Brauer, G. 143 (1993) 301 cation of code scaling, applicability and Eto, M., see Oku, T. 143 (1993) 239 uncertainty methodology to large break LOCA analysis of two loop PWR 143 (1993) 95 Mazzini, M., see Petrangeli, G. 143 (1993) 25 Faidy, C., see Brust, F.W. 143 (1993) 201 Middlebrooks, W.B., D.L. Harrod and R.E. Furukawa, S.-I., see Igusa, T. 143 (1993) 187 Gold, Residual stresses associated with the hydraulic expansion of steam genera- Gao, Z., see Wang, D. 143 (1993) 1 tor tubing into tubesheets 143 (1993) 159 Gao, Z., see Wang, D. 143 (1993) 9 Mohanty, A.K., S.C. Haldar and S. Sen- Garud, Y.S. and K.E. Watkins, 3D gupta, Low Reynolds number flow and stress /deflection analysis of tubesheet heat transfer experiments in 7-rod verti- and U-tubes 143 (1993) 151 cal bundles 143 (1993) 83 Garud, Y.S., Service stresses in expansion Miller, W., see Brocks, W. 143 (1993) 171 transitions of heat-exchanger U-tube joints 143 (1993) 143 Nelson, J.L., see Jones, R.L. 143 (1993) 111 Gilles, P., see Brust, F.W. 143 (1993) 201 Neymotin, L.Y., see Rohatgi, U.S. 143 (1993) 69 Gilman, J.D., see Jones, R.L. 143 (1993) 111 No, H.C. and M. Ishii, Scaling study of in- Gold, R.E., see Middlebrooks, W.B. 143 (1993) 159 core boil-off and heating process 143 (1993) 265 316 Author Index to Volume 143 Noack, H.-D., see Brocks, W. 143 (1993) 171 Veith, H., see Brocks, W. 143 (1993) 171 Oku, T. and M. Eto, Relation between static Wang, D., D. Zhang, D. Dong, Z. Gao, H. and dynamic Young’s modulus of nuclear Li, J. Lin and Q. Su, Experimental study graphites and carbon 143 (1993) 239 and operation experiences of the 5 MW Nuclear Heating Reactor 143 (1993) 9 Petrangeli, G., R. Tononi, F. D’Auria and Wang, D., Z. Gao and W. Zheng, Technical M. Mazzini, The SSN: an emergency sys- design features and safety analysis of the tem based on intentional coolant depres- 200 MWt Nuclear Heating Reactor 143 (1993) 1 surization for PWRs 143 (1993) 25 Wang, D., The design characteristics and ProSek, A., see Mavko, B. 143 (1993) 95 construction experiences of the 5 MWt Nuclear Heating Reactor 143 (1993) 19 Rizzo, F.L., see Cinotti, L. 143 (1993) 295 Wang, W.-C., Tsai-Lin Chen and Chi- Rohatgi, U.S., L.Y. Neymotin and W. Wulff, Hung Hwang, Transient thermal stress Assessment of RAMONA-3B methodol- intensity factors of edge-cracked semi-in- ogy with oscillatory flow tests 143 (1993) 69 finite plates 143 (19932)1 7 Watkins, K.E., see Garud, Y.S. 143 (1993) 151 Sengupta, S., see Mohanty, A.K. 143 (1993) 83 Wulff, W., see Rohatgi, U.S. 143 (1993) 69 Sinha, R., see Igusa, T. 143 (19931)8 7 Song, J.H., see Lee, J.B. 143 (19932)2 9 Yanagisawa, K., Behaviour of small-sized Stierli, F., see Aksan, S.N. 143 (19932)4 5 BWR fuel under reactivity initiated acci- Stritar, A., see Mavko, B. 143 (1993) 95 dent conditions in comparison with stan- Su, Q., see Wang, D. 143 (1993) 9 dard BWR fuel 143 (1993) 285 Tononi, R., see Petrangeli, G. 143 (1993) 25 Zhang, D., see Wang, D. 143 (1993) 9 Tsai-Lin Chen, , see Wang, W.-C. 143 (1993) 217 Zheng, W., see Wang, D. 143 (1993) 1 Nuclear Engineering and Design 143 (1993) 317-318 317 North-Holland Subject Index to Volume 143 Analysis of piping with hysteretic supports Thermal and fluid design using response spectra, T. Igusa, R. Sinha, E. Kokubo, S.-I. Furukawa and The SSN: an emergency system based on J.-1. Kawahata 143 (1993) 187 Comparisons between finite-element analy- intentional coolant depressurization for sis predictions and pipe fracture experi- PWRs, G. Petrangeli, R. Tononi, F. D’Auria and M. Mazzini 143 (1993) 25 ments, F.W. Brust, J. Ahmad, B. Brick- Simulating the mixing of helium and air by stad, C. Faidy and P. Gilles 143 (1993) 201 Transient thermal stress intensity factors of mixing salt water and fresh water in a edge-cracked semi-infinite plates, W.-C. scaled enclosure, Hsu-Wen Chiang and S. C.A. Jones 143 (1993) 55 Wang, Tsai-Lin Chen and Chi-Hung Assessment of RAMONA-3B methodology Hwang 143 (19932)1 7 with oscillatory flow tests, U.S. Rohatgi, Relation between static and dynamic L.Y. Neymotin and W. Wulff 143 (1993) 69 Young’s modulus of nuclear graphites and carbon, T. Oku and M. Eto 143 (1993) 239 Low Reynolds number flow and heat trans- fer experiments in 7-rod vertical bundles, A.K. Mohanty, S.C. Haldar and S. Sen- Materials properties gupta 143 (1993) 83 Application of code scaling, applicability and Relation between static and dynamic uncertainty methodology to large break Young’s modulus of nuclear graphites LOCA analysis of two loop PWR, B. and carbon, T. Oku and M. Eto 143 (19932)3 9 Mavko, A. Stritar and A. ProSek 143 (1993) 95 Considerations about irradiation-induced Boil-off experiments with the PSI-NEPTUN precipitates in Soviet type reactor pres- facility: Analysis and code assessment sure vessel steels, G. Brauer and F. Eich- overview report, S.N. Aksan, F. Stierli horn 143 (19933)0 1 and G.Th. Analytis 143 (1993) 245 Scaling study of in-core boil-off and heating Mechanical design, component fabrication and testing process, H.C. No and M. Ishii 143 (1993) 265 Fracture mechanics investigations on a pipe Engineering mechanics with a circumferential flaw supported by FEM, W. Brocks, W. Miller, H.-D. Controlling stress corrosion cracking in Boil- Noack and H. Veith 143 (1993) 171 ing Water Reactors, R.L. Jones, J.D. Comparisons between finite-element analy- Gilman and J.L. Nelson 143 (1993) 111 sis predictions and pipe fracture experi- Service stresses in expansion transitions of ments, F.W. Brust, J. Ahmad, B. Brick- heat-exchanger U-tube joints, Y.S. Garud 143 (1993) 143 stad, C. Faidy and P. Gilles 143 (1993) 201 3D stress /deflection analysis of tubesheet and U-tubes, Y.S. Garud and K.E. Watkins 143 (1993) 151 Reactor concepts and systems analysis Residual stresses associated with the hy- draulic expansion of steam generator tub- Technical design features and safety analysis ing into tubesheets, W.B. Middlebrooks, of the 200 MWt Nuclear Heating Reac- D.L. Harrod and R.E. Gold 143 (1993) 159 tor, D. Wang, Z. Gao and W. Zheng 143 (1993) 1 Fracture mechanics investigations on a pipe Experimental study and operation experi- with a circumferential flaw supported by ences of the 5 MW Nuclear Heating Re- FEM, W. Brocks, W. Miiller, H.-D. actor, D. Wang, D. Zhang, D. Dong, Z. Noack and H. Veith 143 (1993) 171 Gao, H. Li, J. Lin and Q. Su 143 (1993) 9 318 Subject Index to Volume 143 The design characteristics and construction Nuclear safety experiences of the 5 MWt Nuclear Heat- ing Reactor, D. Wang 143 (1993) 19 The SSN: an emergency system based on PWSCC in the tube expansion zone — an intentional coolant depressurization for overview, P. Hernalsteen 143 (1993) 131 PWRs, G. Petrangeli, R. Tononi, F. The Inherently Safe Immersed System (ISIS) D’Auria and M. Mazzini 143 (1993) 25 reactor, L. Cinotti and F.L. Rizzo 143 (1993) 295 Simulating the mixing of helium and air by mixing salt water and fresh water in a Safeguard engineering scaled enclosure, Hsu-Wen Chiang and S. C.A. Jones 143 (1993) 55 Controlling stress corrosion cracking in Boil- Assessment of RAMONA-3B methodology ing Water Reactors, R.L. Jones, J.D. with oscillatory flow tests, U.S. Rohatgi, Gilman and J.L. Nelson 143 (1993) 111 L.Y. Neymotin and W. Wulff 143 (1993) 69 Application of code scaling, applicability and Layout of nuclear facilities uncertainty methodology to large break LOCA analysis of two loop PWR, B. The Inherently Safe Immersed System (ISIS) Mavko, A. Stritar and A. ProSek 143 (1993) 95 reactor, L. Cinotti and F.L. Rizzo 143 (1993) 295 Boil-off experiments with the PSI-NEPTUN facility: Analysis and code assessment Core physics and fuel design overview report, S.N. Aksan, F. Stierli and G.Th. Analytis 143 (1993) 245 Behaviour of small-sized BWR fuel under reactivity initiated accident conditions in comparison with standard BWR fuel, K. Yanagisawa 143 (1993) 285

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