Nuclear Reactor Thermal-Hydraulics Vol 3 [7th Intl Meeting]
Rio de Janeiro, Brasil, October , ,. Also published in the journal of Industrial Heat Engineering, vol. Begell house Inc. Kerntechnik, 64 pp Applications of Accelerator Technology, Nov. Symposium on Globalization of Nuclear Activities. Rio de Janeiro, June , Kerntechnik, 62, , 4, pp Nuclear Engineering and Design, , Kryukov; Sokolov, M. Kerntechnik, Vol.
SD-1, pp. ANS Proceedings, Vol. Nuclear Technology, Vol. Revista Brasileira de tecnologia, Vol.
CNPq, Revista Brasileira de Tecnologia, Vol. The Nucleus, 8, No. International seminar on the safety research needs for Russian- designed reactors: material presented at the international seminar : Tokyo, Japan , PSA based plant modifications and backfits, Latent failures of safety systems, A generic study performed by the Principal Working Group 1 on operating experience and human factors, Technical note on ex-vessel core melt debris coolability and steam explosions, Relevant thermal hydraulic aspects of advanced reactors design: status report, CSNI Status summary on utilization of best-estimate methodology in safety analysis and licensing, Catalogue of generic plant states leading to core melt in PWRs: includes appendix 1: detailed description of sequences leading to core melt, Evaluation of the separate effects tests set validation matrix, Computer and compiler effects on code results: status report, Report of the task group on the seismic behaviour of structures: status report, Also referenced as: AECL Also referenced as: PSI Probabilistic structure integrity analysis and its relationship to deterministic analysis : Stockholm, Sweden , Boron reactivity transients: proceedings of a specialist meeting : State College, Pa.
Safety of the nuclear fuel cycle: topical meeting : Cadarache, France , The Chernobyl reactor accident source term: development of a consensus view, In-vessel core degradation code validation matrix, Report of the task group reviewing national and international activities in the area of ageing of nuclear power plant concrete structures, Leak before break in reactor piping and vessels: specialist meeting Lyons, France , Human factor related common cause failure: part 1, Evidence of aging effects on certain safety-related components: contributions of participating countries, Vol 2.
Evidence of aging effects on certain safety-related components: summary and analysis, Vol 1. Report on round robin activities on the calculation of crack opening behaviour and leak rates for small bore piping components, Overview of current approaches regarding the use of water to cool a molten core in the containment in ten OECD member countries, Summary and conclusions: specialist meeting on selected containment severe accident management strategies : Stockholm, Sweden , Core debris cooling with flooded vessel or core-catcher heat exchange coefficients under natural convection, Specific features of cesium chemistry and physics affecting reactor accident source term predictions, Also referenced as: SKI report Task reliability data collection and analysis to support probabilistic safety analysis PSA : an evaluation of questionnaire results, Risk-based management of safety systems' availability: risk based configuration control, In-Vessel core debris cooling through external flooding of the reactor pressure vessel: situation report, Task3: New man-machine interfaces in nuclear power plants.
PartII: Appendices, Also referenced as: GRS KfK Separate effects test matrix for thermal-hydraulic code validation, Vol. International standard problem distribution of hydrogen within the HDR containment under severe accident conditions: final comparison report, Also referenced as: KfK Instrumentation for accident management in containment: a preliminary technical document, Source term uncertainties: recent developments in understanding fission product behaviour, Workshop on aerosol behaviour and thermal-hydraulics in the containment, Fontenay-aux-Roses, technical summary.
The Complementary roles of fracture mechanics and non-destructive examination in the safety assessment of components: proceedings of a Workshop : Wuerenlingen, Switzerland , Regulatory practices on pressurized thermal shock: results of an international survey, International practices for analyzing, regulating and improving human performance of maintenance activities at nuclear power plants, Specialist meeting on pump performance and reliability: meeting proceedings : Cologne, Germany , Current national source term positions and practices in OECD member countries, International workshop on boiling water reactor stability: proceedings : Holtsville, New York , Workshop on aerosol behaviour and thermal-hydraulics in the containment: proceedings : Fontenay-aux-Roses, France , Santa-Fe, New Mexico, September , Report on the use of probabilistic safety assessment for nuclear power plant safety management: utilities' reply to a questionnaire, Human reliability in probabilistic risk assessments: use of operating experience, Generic study of events involving loss of residual heat removal function: potential loss of RHR function on PWRs, Catton and M.
Mori, K. Kosako, Y. Oyama, Y. Ikeda, C. Konno, H. Maekawa, T. Abdou, E. Bennett, M. Youssef and T. Kumar, C. Konno, K.
Ikeda, S. Tsuda, K. Nakagawa, T. Mori, T. Konno, Y Ikeda, K. Oyama, and H. Bennett, A. Bennett, K. Porges, M. Abdou, and H.
Ralph A. Nelson, Jr. Vita: Publications
Maekawa and M. Kuan, M. Abdou, and S. Xu, M. Abdou, and A. Abdou, and M. Abdou, and R. Ying, S. Federici, A. Billone, C. Wu, S. Cho, A. Raffray, S. Davidson, B. Ripin, M. Jun, M. Abdou, et. Tehranian, M. Abdou and M. Logan, A. Anderson, M. Tobin, V. Schrock, W. Bangerter, R. Tillack, N. Ghoniem, L. Waganer, D. Driemeyer, G. Linford, D. Catton, A. Song, M. Gorbis, A. Raffray, A. Badawi, S. Cho, and M. Ghoniem, A.
Abdou and L. Jun and M. Maekawa, A. Linford, H. Weitzner, M. Nakamura, Y. Maekawa, K.
Kosako, M. Ikeda and T. McCarthy and M. Kunugi, M. Kosako, T. Nakamura, A. Abdou and E. Konno, T. Kumar and M. Raffray, Z. Gorbis and M. Gohar, H. Attaya, M.
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Lin, C. Hohnson, S.