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Nuclear Engineering and Design 1994: Vol 152 Index PDF

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Preview Nuclear Engineering and Design 1994: Vol 152 Index

Nuclear Engineering and Design Nuclear Engineering and Design 152 (1994) 413-414 Author Index of Volume 152 Abdel-Khalik, S.I., see Ghiaasiaan, S.M. 152 (1994) 379 Epstein, M., A natural convection model of Araseki, H., S. Kotake, Numerical method molten pool penetration into a melting for analysis of turbulent liquid metal mag- miscible substrate (1994) 319 netohydrodynamic flow 152 (1994) 231 Eripret, C., see Lidbury, D.P.G. 2 (1994) 1 Aritomi, M., see Chiang, J.-H. 152 (1994) 263 Eripret, C., and G. Rousselier, First spinning Austregesilo, H., see Vijayan, P.K. 152 (1994) 331 cylinder test analysis by using a local ap- Auflick, L.J., see Galyean, W.J. 152 (1994) 159 proach to fracture 152 (1994) Azzopardi, B.J., The effect of a plate axial to the flow on the liquid distribution in annu- Fujimoto, N., see Maruyama, S. 152 (1994) lar two-phase flow 152 (1994) 257 Galyean, W.J., D.L. Kelly, J.A. Schroeder, Bass, B.R., see Sievers, J. 152 (1994) 19 J.L. Auflick, H.S. Blackman, D.I. Gertman Battiste, R.L., see Poole, A.B. 152 (1994) 57 and L.N. Hanley, Intersystem LOCA risk Berg, H.P., and K. Harnack, The system for assessment: methodology and results 152 (1994) transportation and handling of radioactive Gardner, L., see Wright, D.J. 152 (1994) waste packages in the planned Konrad Gertman, D.I., see Galyean, W.J. 152 (1994) repository 152 (1994) 389 Ghiaasiaan, $.M., R.E. Turk and S.I. Abdel- Berger, F.P., and A. Ijaz, Loading of tubular Khalik, Countercurrent flow limitation in filters in AGR 152 (1994) 91 inclined channels with bends 152 (1994) 3 Bilby, B.A., see Lidbury, D.P.G. 152 (1994) 1 Gédller, B., Protection against missiles due to Blackman, H.S., see Galyean, W.J. 152 (1994) 159 a failing PWR pressure vessel 152 (1994) Guido-Lavalle, G., P. Carrica, A. Clausse and M.K. Qazi, A bubble number density Carbajo, J.J., MELCOR sensitivity studies for constitutive equation 152 (1994) 2 a low-pressure short-term station blackout Guido-Lavalle, G., see Qazi, M.K. 152 (1994) 22 at the Peach Bottom plant, 152 (1994) 287 Gupta, A.K.,, and H.A. Megahed, Two Carrica, P., see Guido-Lavalle, G. 152 (1994) 213 methods for seismic analysis of non-classi- Chang, C.-S., see Ting, K. 152 (1994) 135 cally damped systems 152 (1994) Chang, K.-K., see Ting, K. 152 (1994) 135 Chapman, J.C., see Larson, T.K. 152 (1994) 277 Hanley, L.N., see Galyean, W.J. 152 (1994) Chatoorgoon, V., see Zeitoun, O. 152 (1994) 243 Harnack, K., see Berg, H.P. 152 (1994) Chiang, J.-H., M. Aritomi and M. Mori, Hendrich, W.R., see Poole, A.B. 152 (1994) Transient behavior of natural circulation Howard, I.C., see Lidbury, D.P.G. 152 (1994) for boiling two-phase flow (flow after Hwang, W.G., see Jhung, M.J. 152 (1994) pump trip) 152 (1994) 263 Clausse, A., see Guido-Lavalle, G. 152 (1994) 213 Ijaz, A., see Berger, F.P. 152 (1994) Clausse, A., see Qazi, M.K. 152 (1994) 225 Clinard, J.A., see Poole, A.B. 152 (1994) 57 Jhung, M.J., K.B. Park, W.G. Hwang, Dy- namic response of reactor internals to pipe Depiante, E.V., Stability analysis of a liquid- breaks 152 (1994) metal reactor and its primary heat trans- port system 152 (1994) 361 Kawai, M. 121 DeWall, K.G.,, see Watkins, J.C. 152 (1994) 67 Kelly, D.L., see Galyean, W.J. 152 (1994) 159 414 Author Index | Nuclear Engineering and Design 152 (1994) 413-414 Kotake, S., see Araseki, H. 152 (1994) 231 Rothberg, O.0., see Watkins, J.C. 152 (1994) 67 Rousselier, G., see Eripret, C. 152 (1994) 11 Larson, T.K., C.H. Oh and J.C. Chapman, Flooding in a thin rectangular slit geome- Schroeder, J.A., see Galyean, W.J. 152 (1994) 159 try representative of ATR fuel assembly Sharples, J.K., see Wright, D.J. 152 (1994) 39 side-plate flow channels 152 (1994) 277 Sherry, A.H., see Lidbury, D.P.G. 152 (1994) 1 Li, Z.H., see Lidbury, D.P.G. 152 (1994) 1 Sherry, A.H., see Wright, D.J. 152 (1994) 39 Lidbury, D.P.G., A.H. Sherry, B.A. Bilby, Shoukri, M., see Zeitoun, O. 152 (1994) 243 1.C. Howard, Z.H. Li and C. Eripret, Pre- Sievers, J., and B.R. Bass, Comparative as- diction of the first spinning cylinder test sessment of project FALSIRE— results 152 (1994) 19 using continuum damage mechanics 152 (1994) 1 Steele, R., see Watkins, J.C. 152 (1994) 67 Lin, Y.N., and C. Pan, Non-linear analysis Sudo, Y., see Maruyama, S. 152 (1994) 183 for a natural circulation boiling channel 152 (1994) 349 Maruyama, S., N. Fujimoto, Y. Sudo, T. Tang, Y., Rocking response of tanks con- Murakami and S. Fujii, Evaluation of core taining two liquids 152 (1994) 103 thermal and hydraulic characteristics of Ting, K., C.-S. Chang and K.-K. Chang, HTTR 152 (1994) 183 Alternating method applied to analyse Megahed, H.A., see Gupta, A.K. 152 (1994) 117 Mode-III fracture problems with multiple Mori, M. 263 cracks in an infinite domain 152 (1994) 135 Murakami, T., see Maruyama, S. 152 (1994) 183 Tseng, C.M., Second trip system for NRU No, H.C., see Oh, D.Y. 152 (1994) 197 research reactor 152 (1994) 175 Turk, R.E., see Ghiaasiaan, S.M. 152 (1994) 379 Oh, C.H., see Larson, T.K. 152 (1994) 277 Oh, D.Y., and H.C. No, Determination of Vijayan, P.K., H. Austregesilo, Scaling laws the minimal number and optimal sensor for single-phase natural circulation loops 152 (1994) 331 location in a nuclear system with fixed incore detectors 152 (1994) 197 Watkins, J.C.,, R. Steele, Jr., K.G. DeWall, Pan, C., see Lin, Y.N. 152 (1994) 349 G.H. Weidenhamer and O.O. Rothberg, Park, K.B., see Jhung, M.J. 152 (1994) 79 NRC test results and operations experience Poole, A.B., J.A. Clinard, R.L. Battiste and provide insights for a new gate valve stem force correlation 152 (1994) 67 W.R. Hendrich, Fracture mechanics and full scale pipe break testing for the Depart- Weidenhamer, G.H., see Watkins, J.C. 152 (1994) 67 Wright, D.J., J.K. Sharples, A.H. Sherry and ment of Energy’s new production reactor- heavy water reactor 152 (1994) 57 L. Gardner, Effect of biaxial loading on the fracture behaviour of a ferritic steel com- Qazi, M.K., see Guido-Lavalle, G. 152 (1994) 213 ponent 152 (1994) 39 Qazi, M.K., G. Guido-Lavalle and A. Clausse, Void fraction along a vertical Zeitoun, O., M. Shoukri and V. Chatoor- heated rod bundle under flow stagnation goon, Measurement of interfacial area con- conditions 152 (1994) 225 centration in subcooled liquid—vapour flow 152 (1994) 243 Fusion Engineering and Design ELSE3AVT NI 4 ER Nuclear Engineering and Design 152 (1994) 415-416 Subject Index of Volume 152 Thermal and fluid design A natural convection model of molten pool penetration into a melting miscible sub- MELCOR sensitivity studies for a low-pressure, strate, M. Epstein 152 (1994) 319 short-term station blackout at the Peach Non-linear analysis for a natural circulation Bottom plant, J.J. Carbajo 152 (1994) 287 boiling channel, Y.N. Lin and C. Pan 152 (1994) 349 Scaling laws for single-phase natural circula- Countercurrent flow limitation in inclined tion loops, P.K. Vijayan and H. Austrege- channels with bends, S.M. Ghiaasiaan, silo 152 (1994) 331 R.E. Turk and S.I. Abdel-Khalik 152 (1994) 379 Heat conduction and transfer Engineering mechanics A natural convection model of molten pool penetration into a melting miscible sub- Rocking response of tanks containing two strate, M. Epstein 152 (1994) 319 liquids, Y. Tang 152 (1994) 103 Stability analysis of a liquid-metal reactor and Two methods for seismic analysis of non-clas- its primary heat transport system, E.V. sically damped systems, A.K. Gupta and Depiante 152 (1994) 361 H.A. Megahed 152 (1994) 117 comparative study of anisotropic creep Fluid dynamics theories, M. Kawai 152 (1994) 121 A bubble number density constitutive equa- tion, G. Guido-Lavalle, P. Carrica, A. Materials properties Clausse and M.K. Qazi 152 (1994) 213 Void fraction along a vertical heated rod Prediction of the first spinning cylinder test bundle under flow stagnation conditions, using continuum damage mechanics, M.K. Qazi, G. Guido-Lavalle and A. D.P.G. Lidbury, A.H. Sherry, B.A. Bilby, Clausse 152 (1994) 225 I.C. Howard, Z.H. Li and C. Eripret 152 (1994) 1 Numerical method for analysis of turbulent First spinning cylinder test analysis by using liquid metal magnetohydrodynamic flow, a local approach to fracture, C. Eripret H. Araseki and S. Kotake 152 (1994) 231 and G. Rousselier 152 (1994) 11 Measurement of interfacial area concentra- Comparative assessment of project FAL- tion in subcooled liquid—vapour flow, O. SIRE—results, J. Sievers and BR. Zeitoun, M. Shoukri and V. Chatoorgoon 152 (1994) 243 Bass 152 (1994) 19 The effect of a plate axial to the flow on the Effect of biaxial loading on the fracture be- liquid distribution in annular two-phase haviour of a ferritic steel component, D.J. flow, B.J. Azzopardi 152 (1994) 257 Wright, J.K. Sharples, A.H. Sherry and L. Transient behavior of natural circulation for Gardner 152 (1994) 39 boiling two-phase flow (flow after pump Fracture mechanics and full scale pipe break trip), J.-H. Chiang, M. Aritomi and M. testing for the Department of Energy’s Mori 152 (1994) 263 new production reactor-heavy water reac- Flooding in a thin rectangular slit geometry tor, A.B. Poole, J.A. Clinard, R.L. Bat- representative of ATR fuel assembly side- tiste and W.R. Hendrich 152 (1994) 57 plate flow channels, T.K. Larson, C.H. Oh comparative study of anisotropic creep and J.C. Chapman 152 (1994) 277 theories, M. Kawai 152 (1994) 121 416 Subject Index | Nuclear Engineering and Design 152 (1994) 415—416 Alternating method applied to analyse Mode- Reactor concepts and systems analysis III fracture problems with multiple cracks Intersystem LOCA risk assessment: method- in an infinite domain, K. Ting, C.-S. ology and results, W.J. Galyean, D.L. Chang and K.-K. Chang 152 (1994) 135 Kelly, J.A. Schroeder, J.L. Auflick, H.S. Blackman, D.I. Gertman and LN. Mechanical design, component fabrication and testing Hanley 152 (1994) 159 Second trip system for NRU research reactor, Prediction of the first spinning cylinder test C.M. Tseng 152 (1994) 175 using continuum damage mechanics, Evaluation of core thermal and hydraulic D.P.G. Lidbury, A.H. Sherry, B.A. Bilby, characteristics of HTTR, S. Maruyama, 1.C. Howard, Z.H. Li and C. Eripret 152 (1994) N. Fujimoto, Y. Sudo, T. Murakami and First spinning cylinder test analysis by using S. Fujii 152 (1994) 183 a local approach to fracture, C. Eripret and G. Rousselier 152 (1994) Safeguard engineering Comparative assessment of project FAL- SIRE—results, J. Sievers and B.R. Determination of the minimal number and Bass 152 (1994) optimal sensor location in a nuclear sys- Effect of biaxial loading on the fracture be- tem with fixed incore detectors, D.Y. Oh haviour of a ferritic steel component, D.J. and H.C. No 152 (1994) 197 Wright, J.K. Sharples, A.H. Sherry and L. Structural design, construction methods and testing Gardner 152 (1994) Fracture mechanics and full scale pipe break Protection against missiles due to a failing testing for the Department of Energy’s PWR pressure vessel, B. Géller 152 (1994) 147 new production reactor-heavy water reac- tor, A.B. Poole, J.A. Clinard, R.L. Bat- Nuclear waste management and disposal tiste and W.R. Hendrich 152 (1994) The system for transportation and handling NRC test results and operations experience provide insights for a new gate valve stem of radioactive waste packages in the planned Konrad repository, H.P. Berg force correlation, J.C. Watkins, R. Steele, Jr., K.G. DeWall, G.H. Weidenhamer and and K. Harnack 152 (1994) 389 0.0. Rothberg 152 (1994) Nuclear safety Dynamic response of reactor internals to pipe breaks, M.J. Jhung, K.B. Park, W.G. Determination of the minimal number and Hwang 152 (1994) optimal sensor location in a nuclear sys- Loading of tubular filters in AGR, F.P. tem with fixed incore detectors, D.Y. Oh Berger and A. Ijaz 152 (1994) and H.C. No 152 (1994) 197

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