proceedings:2014_igorr16 [IGORR]

November 2014, Bariloche, Argentina

Title	Author(s)
A Core Pressure Drop Monitoring System: Design and implementation at the RA6 Research Reactor	F. Brollo
Adaptation of ANUBIS scheme to SAFARI-1 core characterisation	L. Moloko
ADVANCE IN THE RA-10 REACTOR PROJECT	H. Blaumann
Ageing Management Programme for Research Reactors in Argentina	G. Vega
Ageing Management, Obsolescence and Refurbishment of GHARR-1 Structures, Systems and Components (SSCs)	E.O. Amponsah-Abu
ANALYSIS OF A CORE COOLING FLOW BYPASS EVENT PRODUCED BY SPURIOUS OPENING OF A FLAP VALVE AT THE PRIMARY COOLING CIRCUIT OF THE RA-10 REACTOR	R. Hilal
Analysis of a Loss of Offsite Power Event for the RA-10 Reactor	S. Papadakis
Analysis of an Inadvertent Control Plate Withdrawal Event in the RA-10 Reactor	R. Maturana
Analysis on LCO for On-Power Loading/Unloading Irradiation Targets in a Research Reactor	Hyeonil Kim
CFD Models of the RA-10 RI Facilities: A Useful Tool for Design Support	M. Gramajo
Characterization of UO2-Gd2O3 nuclear fuel obtained by co-precipitation by Transmission Electron Microscopy	I. Gana
CNEA DEVELOPMENTS IN U-Mo-Zry-4 MINIPLATES AND PLATES CO-ROLLING CONTROL	B. Picchetti
COCONEUT: An innovative deterministic neutronic calculation tool for research reactors	J.-G. Lacombe
Conceptual Design of a Compact Nuclear Reactor Core	R.Vignolo
Conceptual Design of a Research Reactor with Monolithic UMo Fuels	J.I. Beliera
Conceptual Design of the Core of an ADS (Accelerator Driven System)	M. Tacca
Contributions of CFD to the analysis of the second shutdown system of the RA-10 research reactor	L. M. Rechiman
Correction factors to apply to fission rates measured by miniature fission chambers in various neutron spectra	B. Geslot
Creativity in Cold Neutron Sources Design	L. Manifacier
CURRENT STATUS OF JRR-3	Y. Kashima
Current Status of the KJRR Project and its Design Features	C.Park
Cyber Security Study for Research Reactors	J. Shin
Density determination of pyrotechnical devices using neutron imaging techniques on the RA-6 reactor	N. Chiaraviglio
DEPLETION ANALYSIS OF THE OPAL REACTOR WITH VESTA	P.Young
Description and Applications of the Neutron Imaging Facility at RA-6	J. Marin
Design and first operation of the DIAMINO (U241AmO2) experiment in OSIRIS MTR for Am-recycling program	S. BENDOTTI, C. NEYROUD, S. BEJAOUI, T. LAMBERT
Design of a calibration beam for detector characterization	J. M. Longhino
Development of Emergency Operating Guidelines for a Research Reactor	Hyeonil Kim
Development of Equipment for Simulating Coolant Flow in a Test Rig	J. T. Hong
Development of Laser Welding Technology for Fabricating Nuclear Fuel Test Rig	C.Y. Joung
Development of Safety Management Portal System for HANARO Research Reactor	Hoan Sung Jung
Deviation from ASME III Code rules for the design of Research Reactors	M. Wesley
Diving in the pool of a Research Reactor Inspection of the natural convection valves of the primary circuit of OSIRIS reactor during summer outage	J.S. Zampa
Dog-Bone Studies In U-Mo-Zry-4 Miniplates Fabrication Process	M. Lopez
Education and Training at Low Power Research Reactor VR-1 for National and International Students and Trainees	Lubomir Sklenka - Czech Republic
ENEA Thermal and Fast Research Reactors utilization for R&D activities at Casaccia Center	M. Sepielli
Expansion of the Cold Neutron Facilities and Reactor Upgrades at the NIST Center for Neutron Research	R. E. Williams
Experimental Investigation of Operational Parameters in the CDTN TRIGA Reactor	A.Z Mesquita
Experimental Study on Downward Two-Phase Flow in Vertical Narrow Rectangular Channel	J.H. Jeong
FPGA Based Reactor Protection System Architecture	C.A. Verrastro
FRM II: Results and experience of the major maintenance shutdown after ten years of operation	A. Pichlmaier
Heat Deposition in Out-Core Devices of Research Reactors after Actuation of a Shutdown System Based on Reflector Tank Draining	H. Meier
High Order Finite Elements for Reactor Calculation. Examples and Comparison with Experimental Results	Carlos R. Grant
Implementation and Utilization of Positron Annihilation Spectrometry Methods at the PULSTAR Reactor	A. I. Hawari
Implementation of a Periodic Safety Review of HANARO Research Reactor	Minjin Kim
Implementation of the Neutron Noise Technique for Measurement of Reactivity in Subcritical of the Low Power Research Reactor RA-4	J. Orso
IMPROVING IMMUNITY OF THE OPAL REACTOR TO ELECTRICAL POWER DISTURBANCES	B. GITTOES
Instrumentation & Control Systems for the Brazilian Multipurpose Reactor - RMB	P. Carvalho
Integral (n,y) Cross-sections Measurement of Standard Light Water Reactors Materials	A. Gruel
Investigation of Mixed Enrichment Core Loadings for the PULSTAR Reactor	A. I. Hawari
IRRADIATION CAPSULE DESIGN TO SUPPORT DOE RESUMPTION OF US 60Co ISOTOPE PRODUCTION	R. Howard
Irradiation Facilities Performance at RA-10	F. Sanchez
Irradiation Loop Facility in RA-10 Reactor	L. Vazquez
Irradiation Requirements for Radioisotope Production	D. Hergenreder
JULES HOROWITZ REACTOR OPERATION IN MOCK-UP MODES	J. Estrade
Jules Horowitz Reactor: organization for the preparation of the commissioning phase and normal operation	J. Estrade
Kinetic Parameters Estimation in the RA-0 Research Reactor	P. Bellino
LEVEL 1 PROBABILISTIC SAFETY ASSESSMENT FOR LICENSING OF RA-10 REACTOR	M. Grinberg
LEVEL 2 AND 3 PROBABILISTIC SAFETY ASSESSMENT FOR LICENSING OF RA-10 REACTOR	C. Mulleady
LORELEI: A future Test Device for LOCA Experiments in the JHR	L. Ferry
Materials Surveillance Programme for the RA10 Research Reactor	R. Versaci
Measurement of Fission Products and Chemical Species released by Experimental Samples irradiated in the Jules Horowitz Reactor	D. Parrat
Measurement of the Xenon-135 Reactivity Evolution after a Shutdown in the RA-3 Research and Production Reactor	P. Bellino
Mechanicals description of RA-10 Reactor and Service Pool and main Core Components	A. Coleff
More than Forty Years of Neutronics Experiments in Critical Facilities of Cadarache Center: From EOLE and MINERVE to the Future ZEPHYR Reactor	S. Cathalau
Neutron Absorbing Glass Microspheres as Second Shutdown System	I. Gana
Neutron and Gamma Shielding Design of the Neutron Guide Primary Shutter in a Research Reactor	A. Maître
Neutron Cold Source Optimization for RA-10 reactor	A. Marquez
Neutron Flux and Reactor Kinetic parameters Calculations in the RA0 Reactor	L. Romero
Neutronic Analysis of the Jamaican SLOWPOKE-2 Research Reactor for the Conversion from HEU to LEU Fuel	H. Dennis
Neutronic Calculation Methodology for Research Reactors	E. Villarino
Neutronic Design of the RA10 Research Reactor´s Core	J.M.Tunon
Neutronic Design of the RMB Research Reactor	J.M.Tunon
Neutronic Simulation of IPR-R1 TRIGA First Configuration using Serpent and MCNP Codes	S. P. de Meireles
New Core with Low-Enriched Uranium Fuel at the Kazakhstan Critical Facility	A. Shaimerdenov
Nuclear Education & Training activity experience at the University of Pavia	A. Salvini
Nuclear Instrumentation System of RA-10	G. Quesada
Numerical Investigation of Cooling in the Pool of the Brazilian Multipurpose Reactor (RMB)	A.Z Mesquita
OPAL Reactor Full 3-D Calculations using the MonteCarlo Code Serpent 2	Diego Ferraro
Operation and Utilisation of Low Power Research Reactor Critical Facility for Advanced Heavy Water Reactor (AHWR)	S. K. De
OPERATION, MAINTENANCE EXPERIENCE AND FUTURE CHALLENGES OF TRIGA RESEARCH REACTOR OF BANGLADESH	M. A. Salam
Optimisation Approach to Asses Seismic Reinforcements of a Low Power Research Reactor	M. Auzas
PARCS Few-group Homogenized Parameters Generation using Serpent Monte Carlo code at the CROCUS Reactor	A. Rais
Preliminary Studies on A New Research Reactor and Cold Neutron Source at NIST	Zeyun Wu
Preparation and Submission of a Manuscript for the Proceedings of the Technical Meeting	A. Malaquias
Production Facilities for Reactor Produced Radioisotopes	J. Merino
RA10 - Utilization-driven Layout	N. De Lorenzo
RA-10 Design Management: Strategic Objectives and Specific Actions	F. Brollo
RA-10 Project Safety Assessment and Licensing Process	P. Ramirez
Relevant Characteristics of the RA-10 I&C Systems	P. Cantero
Relicensing of the SM1 Sub-critical assembly of the Pavia University	L. Strada
Renovation, improvement and experimental validation of the Helium-3 transient rods system for the reactivity injection in the CABRI reactor	B. Duc
Replacement of the Oregon State University TRIGA® Reactor Annular Reflector	S. Todd Keller
Research Institute of Atomic Reactors	D. Fomin
Research Reactor Spent Fuel Management in Argentina	L. Mottillo
Review of low-power research reactor developed for education and training	In-Cheol Lim - Korea
RMB: THE NEW BRAZILIAN MULTIPURPOSE RESEARCH REACTOR	J.A. Perrotta
Simplified Method For Thermal-Hydraulic Design And Evaluation Of Research Reactor Core, Coupled With Neutronic Montecarlo Calculation	M.A.N Giménez
SIREx: Instrumentation System for Research Reactors	F.D. Rossi Mescolatti
Start-up of a New Storage Facility for Spent Fuel from Research Reactors at CNEA	O. Novara
Status of uranium targets irradiation in MARIA reactor for molybdenum production	G. Krzysztoszek
The Enhancement of VR-1 Reactor Utilization for Practical Education Using Portable Neutron Generator	J. Rataj
The IPEN/MB-01 zero power reactor and the LABGENE reactor experimental programme	P. Piovezan
The Jules Horowitz Reactor: A new high performance MTR (Material Testing Reactor) working as an International User Facility in support to Nuclear Industry, Public Bodies and Research Institutes	G. Bignan
The RMB Research Reactor Project	C. Mazufri
Thermal-Hydraulic Aspects for the Upgrade of a Research Reactor	C. Pavon
Thermal-hydraulic aspects of RMB design	J. Lupiano Contreras
TRACE Code Application to Low Operating Pressure Research Reactor Safety Analysis	A. Rais
Trace element Content of Zingiber Officinalis and Salvia Officinalis plants from Algeria	Z.Lamari
Transmutation Experimental Facility for Research and Development of Accelerator-Driven System in JAEA	K. Tsujimoto
Use of Pulse-Mode Neutron Flux-Change-Rate as a Trip Condition in a Nuclear Reactor	F.N. Ferrucci
Use Virtual Environments for Training in Nuclear Facilities	P. Carvalho
Utilization of the Dalat Research Reactor After Its Core Conversion	N. Nhi Dien
Utilization of the High Flux Isotope Reactor at Oak Ridge National Laboratory	D. L. Selby
Utilization, Safety and Aging Management of the High Flux Isotope Reactor at Oak Ridge National Laboratory	R. A. Crone
Wide Range Amplifier for Neutron Flux Measurement	L. Giuliodori