LIST OF EXTENDED SYNOPSIS Number Title of Paper Main Author IAEA-CN-100/1P Simulation of a Typical Accident and Testing of the A. Keffaz Research Reactor’s Safety System IAEA-CN-100/2 A Coupled Calculational System for Optimal in-Core H. Mazrou Fuel Management in Research Reactors IAEA-CN-100/3P The Research Reactor as a Tool in the Master in C. Notari Nuclear Reactors in Argentina IAEA-CN-100/4P Monte Carlo with Burnup Calculation Method for F. Leszczynski RRs IAEA-CN-100/5P Atomistic Modelling of Interdiffusion Barriers in the J.E. Garcés Interphase Al/Umo Based Fuel IAEA-CN-100/6P Licensing and Specific Authorization Programmes C.D Perrin for Research Reactors and Critical Assemblies IAEA-CN-100/7 Regulatory Control of Research Reactors and Critical C. D. Perrin Assemblies in Argentina IAEA-CN-100/ 10 Study of the Effect of Sedimented Particles on the R. Haddad Corrosion Behaviour of Aluminium Clad Spent Fuel During Storage in Water IAEA-CN-100/ 11P A CNS Calculation Line Based On a Monte-Carlo C.A. Lecot Method IAEA-CN-100/ 12 Neutronic Design of a Cold Neutron Source with D.F Hergenreder MCNP IAEA-CN-100/ 13P MCNP Design of High Performance NTD Facilities D.F Hergenreder IAEA-CN-100/ 14 Some Research Reactors Look Similar but They Are C.M. Mazufri Quite Different IAEA-CN-100/15 Reactor Simulator Development Facility for C.A. Operating Personnel Training Etchepareborda IAEA-CN-100/ 16P ANSTO RRR Simulator for Operating Personnel C.A. Training Etchepareborda IAEA-CN-100/ 17 A Risk Perspective for the Replacement Research J. Baron Reactor in Australia IAEA-CN-100/ 18 Neutronic Design of the First Core of the E. Villarino Replacement Research Reactor IAEA-CN-100/19P Providing the Infrastructure or the BNCT N.A. Rico Hiperthermal Neutron Beam IAEA-CN-100/20 Teaching and Training at RA-6 Reactor and their O. Calzeita Larrieu Contribution to the Research Facilities Development Number Title of Paper Main Author IAEA-CN-100/21P The Prompt Gamma Neutron Activation F. Sanchez Analysis Facility at the RA-6 Reactor of the Bariloche Atomic Centre, Argentina IAEA-CN-100/22P Using the RA-6 Reactor for Medical Research H. Blaumann and Clinical Trials: the BNCT Hiperthermal Neutron Beam IAEA-CN-100/23P Usual Control of RA-3 Fuel Assemblies for the G.R. Ruggirello Upgrading the Reactor Power and Fuel Density IAEA-CN-100/24P Electronic Data acquisition System in RA-0, C.A. Murua RA-1, RA-3 and RA-6 RR IAEA-CN-100/25 Reactor Protection System, Diverse Approach C.A Verrastro IAEA-CN-100/ 26P Data Base for Analysis of RA-1 C.M. MS Barberis Decommissioning IAEA-CN-100/27P Measurement of Noble Gases in Research and G.O. Pita Production Nuclear Reactors IAEA-CN-100/28P Delay Neutron Fraction in Low Enrichment G. Estryk Nuclear Fuel, Calculation for RA-3 Reactor Case IAEA-CN-100/29P RA-3 Reactor Power Increase at 10 P.A. Cataldi IAEA-CN-100/30P Decommissioning Planning of RRs in E. Cinat Argentina: the RA-1 IAEA-CN-100/31P Application of Cambell’s Method to wide L.M. Guiliodori Range Neutron Flux Measuring System IAEA-CN-100/32 The Safety Features of the Replacement M. Summerfield Research Reactor IAEA-CN-100/33 Australian Regulatory Licensing and M.A. Kerr Complience Monitoring of the Construction of a Research Reactor IAEA-CN-100/34 Contribution to International Safeguards and H. Boeck Security by a Small University RR IAEA-CN-100/35P Management of All Sorts of Radioactive A. Jalil Wastes Including Those Arising From Decommissioning of Research Reactor IAEA-CN-100/36 Safe Management of Radioactive Wastes M.M. Rahman Originating From the Operation and Utilization of the TRIGA Mark-II Research Reactor in Bangladesh IAEA-CN-100/37P Estimation of Radiological Doses Due to the M.M. Rahman Failure of a Single Fuel Element of a 3 MW (t) TRIGA Mark-II Research Reactor Number Title of Paper Main Author IAEA-CN-100/38P Approach to Development of High-flux A.A. Mikhalevich Research Reactor with Pebble-bed Core IAEA-CN-100/39 Experience with Probabilistic Safety F.L Joppen Assessment for the BR2 Reactor IAEA-CN-100/40P Corrosion Monitoring of Aluminum Alloys in C.F.C. Ms. Neves TRIGA IPR-R1 Research Reactor IAEA-CN-100/41P Eddy Current NDT: A Developed Technology D.A. Alancar for In-Use and Spent Fuel Cladding Examination of TRIGA and MTR Reactors IAEA-CN-100/42P Shielding and Criticality Safety Analyses of a H.M. Dalle Latin American Cask for Transportation and Interim Storage of Spent Fuel From Research Reactors IAEA-CN-100/43 Enhancement in the Utilization of IEA-R1 R. N. Saxena Research Reactor for Isotope Production and for Research IAEA-CN-100/44 Effect of Coupon Orientation on Corrosion L. Ramanathan Behaviour of Aluminium Alloy Coupons in the Spent Fuel Storage Section of the IEA-R1 Research Reactor Pool IAEA-CN-100/45 The New IPEN-CNEN/SP Neutron Powder C.B.R. Parente Diffractometer IAEA-CN-100/46P Development of MTR-Type Fuel Using UO2 W.B Ferraz Microspheres Dispersed in Stainless IAEA-CN-100/47P Experience Related to Refurbishment and A.J. Soares Modifications of Brazilian IEARI Research Reactor IAEA-CN-100/48 Safety Culture Assessment Programme: P.S.P. de Olivieira Statistical Analysis of a Survey Conducted at the IEA-R1 Brazilian Research Reactor IAEA-CN-100/49P Thermal-Hydraulic Design of a Fuel Mini- W.M. Torres Plates Irradiator for the IEA-R1 Research Reactor IAEA-CN-100/50P Benchmark Measurements and Calculations of H.M. Dalle U3Si2-Al MTR Fuel Plates With Burned Fuel IAEA-CN-100/53 Challenges in Updating a Generic Safety D. J Winfield Analysis Report after 22 Years of Technological and Regulatory Progress IAEA-CN-100/54P Optimization of Safety System Test Frequency D. J Winfield IAEA-CN-100/55 Geochronology by the 40Ar/39Ar Method at K. Perez de Arce the Sernageomin Laboratory, Santiago, Chile Number Title of Paper Main Author IAEA-CN-100/56P Fuel Burnup Measurements using Gamma C. Pereda Spectrometry Technique IAEA-CN-100/57P Utilization of the IEA-R1 Reactor for DNA M.R. Gual Irradiation IAEA-CN-100/58 Improving of Safe Operation and New Open L. Slenka Policy at VR-1 Reactor IAEA-CN-100/59 Extensive Utilization of Training Reactor VR-1 K. Matejka IAEA-CN-100/60P Research Reactor LVR-15 – Operation and Use J. Kysela IAEA-CN-100/61 Statistic Processing of the Calculated Reaction Z. Lahodova Rates IAEA-CN-100/62 Innovation in Radioactive Wastewater-Stream A. Karameldin Management IAEA-CN-100/63P Storage and Encapsulation System of Spent D. Bedrose Fuel in the Egyptian Research Reactor IAEA-CN-100/64 Transient Thermal Hydraulic Modeling of S.E. El-Morshdy ETRR-2 for Off-Site Power Loss IAEA-CN-100/65P A Proposed Nuclear Safeguards System for a A.A. Hamed Decommissioned Nuclear RR IAEA-CN-100/66 Possible Merits of a EU-Funded RTD Activity C. Kirchsteiger on PSA for Research IAEA-CN-100/67 FIR1 Reactor in Service for Boron Neutron I.H. Auterinen Capture Therapy (BNCT) and Isotope Production IAEA-CN-100/68P FIR1 Reactor and the Plans for the Spent Fuel S. Salmenhaara Management IAEA-CN-100/69 Safety Requirements Applied to Research H. Abou Yehia Reactors in France IAEA-CN-100/70 Assessment of the Safety Options for the Jules D. Rive Horowitz Reactor (RJH) IAEA-CN-100/71P Improving the Balance between Operators’ C. Eybert- Responsibility and Nuclear Safety Authority Prudhomme Control for research Facilities IAEA-CN-100/72 Safety Aspects of Cold Neutron Sources in K.H. Gobrecht Research Reactors IAEA-CN-100/74P Radiological Characterization of a Research L Pillette-Cousin Reactor prior to Stage-3 Decommissioning: the Example of the Triton Facility IAEA-CN-100/75 Implementation of Stage-3 Decommissioning L Pillette-Cousin of the Triton Facility IAEA-CN-100/76P On the Decommissioned IRT-3M Research S.P. Abramidze Reactor in Georgia Number Title of Paper Main Author IAEA-CN-100/77P Decommissioning of the Prototype Fast breeder I. Hillebrand Reactor KNK in Germany IAEA-CN-100/80 Eight Years of Neutron Activation Analysis in B.J.B. Nyarko Ghana Using a Low Power Research Reactor , B.J.B. Nyarko IAEA-CN-100/81 Encapsulation of Nuclear Spent Fuel for Semi- S. Tözsér dry Storage at the BRR IAEA-CN-100/82P Updating and Expanding IAEA Reliability S.C. Kim Database for Research Reactor PSA IAEA-CN-100/83 International Decommissioning Strategies L. Jova Sed IAEA-CN-100/84 International Radiation Safety L. Jova Sed Recommendations on Decommissioning IAEA-CN-100/85 Indian Experience in Neutron Beam M. Ramanadham Utilization: In-house and Collaborative Programs IAEA-CN-100/86P Gaseous Waste Management in Indian K.G. Gandhi Research Reactors IAEA-CN-100/87 Engineering Consideration and Experience A.V. Kharpate Related to Refurbishment and Safety Up gradation of 40 MWt Research Reactor CIRUS IAEA-CN-100/88P Containment Isolation Devices for Nuclear P.S. Shetty Reactors IAEA-CN-100/89 Comprehensive in-Service inspection of Kartini S. Syarip Reactor Tank Liner and Fitness for Continued Operation IAEA-CN-100/90P Investigation on Control Rod Interaction in a T. Taryo Conceptual MTR-Type Reactor IAEA-CN-100/92P Training and Qualification of Reactor L.Y. Pandi Operating Personnel in Indonesia IAEA-CN-100/93P Indonesian Regulation on RR Modification L.Y. Pandi IAEA-CN-100/94P Utilization of 4 MW Tehran Research Reactor A.R. Ghahremani by Production of Industrial and Medical Radioisotopes IAEA-CN-100/95 Development of a Centralized Waste M.