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2342475184
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The Design and Safety Features of the IRIS Reactor
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Kling, C.L., Carelli, Finnicum, M.D., Alzbutas, R., Maioli, A., Barra, M., Ghisu, M., Leva, C., Kumagai, Y., PRA Improves IRIS Plant Safety-by-Design™, Proc. Intl. Congress on Advances in Nuclear Power Plants 2005 (ICAPP '05), Seoul, Korea, May 15-19, 2005, Paper 5xxxx.
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Kling, C.L., Carelli, Finnicum, M.D., Alzbutas, R., Maioli, A., Barra, M., Ghisu, M., Leva, C., Kumagai, Y., "PRA Improves IRIS Plant Safety-by-Design™," Proc. Intl. Congress on Advances in Nuclear Power Plants 2005 (ICAPP '05), Seoul, Korea, May 15-19, 2005, Paper 5xxxx.
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6
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34249035762
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IRIS Small Break LOCA Phenomena Identification and Ranking Table (PIRT)
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Seoul, Korea, May 15-19, Paper 5201
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Larson, T.K., Moody, F.J., Wilson, G.E., Brown, W.L., Frepoli, C., Hartz, J., Woods, B.G., Oriani, L., "IRIS Small Break LOCA Phenomena Identification and Ranking Table (PIRT)," Proc. Intl. Congress on Advances in Nuclear Power Plants 2005 (ICAPP '05), Seoul, Korea, May 15-19, 2005, Paper 5201.
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Nuclear Power Desalinating Complex with IRIS Reactor Plant and Russian Distillation Desalination Unit
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Dubrovnik, Croatia, May 16-20
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Cogeneration of Electricity and Potable Water Using The International Reactor Innovative And Secure (IRIS) Design
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10
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34249012528
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Social, Economic and Environmental Assessment of Energy and Water Desalination Options for the Brazilian Polygon of Draught Using the IRIS Reactor
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Dubrovnik, Croatia, May 16-20
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th Intl. Conf. on Nuclear Option in Countries with Small and Medium Electricity Grids, Dubrovnik, Croatia, May 16-20, 2004.
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(2004)
th Intl. Conf. on Nuclear Option in Countries with Small and Medium Electricity Grids
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IRIS Reactor - A Suitable Option to Provide Energy and Water Desalination for the Mexican Northwest Region
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Alonso, G.1
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12
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34249074839
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Design and Manufacturing of the IRIS Helical Coil Steam Generators
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Beijing, China, May 16-20, Paper ICONE13-50256
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th International Conference on Nuclear Engineering (ICONE-13), Beijing, China, May 16-20, 2005, Paper ICONE13-50256.
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th International Conference on Nuclear Engineering (ICONE-13)
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13
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34249048989
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Robotised Solutions for IRIS Steam Generator O&M Procedures
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Beijing, China, May 16-20, Paper ICONE 13-50830
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th International Conference on Nuclear Engineering (ICONE-13), Beijing, China, May 16-20,2005, Paper ICONE 13-50830.
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th International Conference on Nuclear Engineering (ICONE-13)
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14
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IRIS Simplified LERF Model
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Miami, FL, October 3-6
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Maioli, A., Finnicum, D. J., and Kumuagai, Y., IRIS Simplified LERF Model, Proc. ANES 2004 Conference, Miami, FL, October 3-6, 2004.
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IRIS Safety System and Equipment Design Verification Test Plan
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Beijing, China, May 16-20, Paper ICONE 13-50468
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th International Conference on Nuclear Engineering (ICONE-13), Beijing, China, May 16-20, 2005, Paper ICONE 13-50468.
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(2005)
th International Conference on Nuclear Engineering (ICONE-13)
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34249018958
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IRIS Safety-by- Design™ and Its Implication to Lessen Emergency Planning Requirements
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International Atomic Energy Agency IAEA, Vienna, Austria, Nov. 15-19, to be published in an IAEA-TECDOC
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Carelli, M.D., Petrovic, B., Ferroni, P., "IRIS Safety-by- Design™ and Its Implication to Lessen Emergency Planning Requirements," IAEA Technical Mtg. 'Definition of Plant Safety Design Options to Cope with External Events', International Atomic Energy Agency (IAEA), Vienna, Austria, Nov. 15-19, 2004, to be published in an IAEA-TECDOC (2005).
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Carelli, M.D.1
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17
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34249008513
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Computational Fluid Dynamics as a Virtual Facility for R&D in the IRIS PROjet: An Overview
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Dubrovnik, Croatia, May 16-20
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th Intl. Conf. on Nuclear Option in Countries with Small and Medium Electricity Grids, Dubrovnik, Croatia, May 16-20, 2004.
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(2004)
th Intl. Conf. on Nuclear Option in Countries with Small and Medium Electricity Grids
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Colombo, E.1
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Ricotti, M.3
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Yan, Y.5
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18
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34249038433
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Improved Anisotropic Turbulence Modeling for CFD Applications in the IRIS Design
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Beijing, China, May 16-20, Paper ICONE13-50143
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th International Conference on Nuclear Engineering (ICONE-13), Beijing, China, May 16-20,2005, Paper ICONE13-50143.
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(2005)
th International Conference on Nuclear Engineering (ICONE-13)
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Baglietto, E.1
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CFD and DNS Methodologies Development for Fuel Bundle Simulations
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Beijing, China, May 16-20, Paper ICONE13-50144
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th International Conference on Nuclear Engineering (ICONE-13), Beijing, China, May 16-20, 2005, Paper ICONE13-50144.
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A Tight Lattice, Epithermal Core Design for the Integral PWR
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Fuel Management Approach in IRIS Reactor
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Design of a 100% MOX Core for IRIS Reactor
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The Economics of IRIS
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Arlington, VA, USA, April 14-18, Paper ICONE 10-22173
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th International Conference on Nuclear Engineering (ICONE-10), Arlington, VA, USA, April 14-18, 2002, Paper ICONE 10-22173.
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th International Conference on Nuclear Engineering (ICONE-10)
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Internal Control Rod Drive Mechanisms, Design Options for IRIS
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Pittsburgh, PA, June 13-17, paper 4315, pp
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IRIS Preliminary PRA Analysis
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Finnicum, D., Maioli, A., Mizuno, Y., Viais, J., Mendoza, G., Alonso, G., IRIS Preliminary PRA Analysis, Proc. GLOBAL 2003, New Orleans, LA, USA, November 16-20, 2003.
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Lessons Learned in Obtaining Efficient and Sufficient Applications of the PIRT Process
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Boyack, B.E., Wilson, G.E., "Lessons Learned in Obtaining Efficient and Sufficient Applications of the PIRT Process," Proc. BE-2004 Topical Meeting, Washington, D.C., USA, November 14-18, 2004.
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International Atomic Energy Agency (IAEA), Guidance for the Evaluation of Innovative Nuclear Reactors and Fuel Cycles. Report of Phase 1A of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), IAEA-TECDOC-1362, June 2003.
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28
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Analysis of Novel Fuel Geometries for the Generation IV IRIS Reactor
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