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    Joint project
    Second Framework for Irradiation Experiments (FIDES‑II)

     

    The NEA Second Framework for Irradiation Experiments (FIDES-II) supports the fuel and material experimental needs of nuclear safety regulators, technical support organisations, research institution...

    Fuel in nuclear safety Nuclear fuel Nuclear science FIDES Nuclear safety research Accident tolerant fuels Reactor fuel performance …
    Published date: 14 March 2023
    Joint project
    Thermodynamics of Advanced Fuels – International Database (TAF-ID) public version

    The TAF-ID public version contains only data already published in open literature. Currently, the following systems are available in the public version:

    • oxide-carbide fuel (U-Pu-O-C, released Decemb...
    Material science Fuel studies Nuclear science Materials science Thermodynamics Thermodynamic data Databases TAF-ID Codes and programs …
    Published date: 23 February 2023
    Joint project
    Thermodynamics of Advanced Fuels - International Database (TAF-ID)

    On this page

    • Why is thermodynamic data for analyses involving nuclear fuel needed?
    • How is thermodynamic data calculated?
    • Available tools for thermodynamic calculations
    • Project organisation
    • TAF-ID i...
    Material science Structural materials Fuel studies Nuclear science Materials science Thermodynamic data TAF-ID …
    Published date: 23 February 2023
    Joint project
    Second Framework for Irradiation Experiments (FIDES‑II)

    The NEA Second Framework for Irradiation Experiments (FIDES-II) supports the fuel and material experimental needs of nuclear safety regulators, technical support organisations, research institutions ...

    Fuel in nuclear safety Nuclear fuel Nuclear science FIDES Nuclear safety research Accident tolerant fuels Reactor fuel performance …
    Published date: 17 January 2023
    Joint project
    Primary Coolant Loop Test Facility (PKL) Project

    PKL facility. Photo: FRAMATOME, Germany

    The Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility [PKL]) is a facility owned and operated by Framatome GmbH (formerly AREVA NP) in Erlange...

    Accident analysis and management Thermal hydraulics Nuclear safety research Accident management
    Published date: 20 December 2022
    Joint project
    Rod Bundle Heat Transfer (RBHT) Project

    Photo: RBHT Test Facility. US NRC.

    Modelling reactor core behaviour under accident conditions with delayed re-introduction of cooling water (commonly referred to as reflood) is a challenge for safety...

    Accident analysis and management Thermal hydraulics Nuclear safety research Accident management
    Published date: 13 December 2022
    Joint project
    Experimental Thermal Hydraulics for Analysis, Research and Innovations in NUclear Safety (ETHARINUS) Project

    PKL facility. Photo: FRAMATOME, Germany

    The Experimental Thermal Hydraulics for Analysis, Research and Innovations in Nuclear Safety (ETHARINUS) project serves the objectives of investigating phenome...

    Accident analysis and management Thermal hydraulics Nuclear safety research Accident management
    Published date: 9 December 2022
    Joint project
    Sandia Fuel Project (SFP)

    Photos: SFP testing. Left: fuel assembly after a Zr fire; right: fire ignition test. SNL/USNRC.

    The goal of the Sandia Fuel Project was to provide experimental data relevant for hydraulic and ignitio...

    Fuel in nuclear safety Nuclear fuel Accident analysis and management Fuel cycle facility safety Nuclear safety research Joint project …
    Published date: 9 December 2022
    Joint project
    Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression at Fukushima Daiichi Nuclear Power Station (TCOFF)

    Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA

    TCOFF Phases

    First Phase (2017-2020)

    The TCOFF project established a framework for the exchange of technical...

    Nuclear science Fission products Fukushima Thermodynamic data Nuclear safety research Safety research …
    Published date: 7 December 2022
    Joint project
    Studsvik Cladding Integrity Project (SCIP)

    Left: Scheme of Studsvik LOCA test facility Right: Microstructure of fragmented nuclear fuel, Studsvik

    On this page

    • SCIP phases
      • First phase (2004-2009)
      • Second phase (2009-2014)
      • Third phase (2014-2...
    Fuel in nuclear safety Nuclear fuel Fuel cycle facility safety Nuclear safety research CSNI Back-end …
    Published date: 7 December 2022
    Joint project
    International Common-cause Failure Data Exchange (ICDE) Project

    Scheme showing the technical scope of NEA ICDE project activities, NEA 

    Common-cause failure (CCF) events can significantly affect the availability of safety systems of nuclear power plants. In recog...

    Risk assessment Nuclear safety research CSNI Probabilistic risk assessment
    Published date: 30 November 2022
    Joint project
    Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF) Project

    Units 1 and 2 End of Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (4th October, 2011). Photo: Tokyo Electric Power Company Holdings

    The Benchmark Study of the Acci...

    Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Accident management …
    Published date: 25 November 2022
    Joint project
    Preparatory Study on Analysis of Fuel Debris (PreADES) Project

    End state of debris in the units 1-3 of Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings. Photo: Japan Atomic Energy Agency

    The Preparatory Study on Analysis of Fuel D...

    Fukushima Accident analysis and management Nuclear safety research CSNI Safety Safety research …
    Published date: 25 November 2022
    Joint project
    Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) Project

    View of the ATLAS experimental loop. KAERI, Korea

    The Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) Project was referenced in The Fukushima Daiichi Nuclear Power Plant Accident...

    Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Accident management …
    Published date: 25 November 2022
    Joint project
    Reduction of Severe Accident Uncertainties (ROSAU) Project

    Left: Test facility for qualification of melt spreading tests. Photo: Argonne National Laboratory (ANL).
    Right: Example of corium melt pouring for a melt spreading preparatory test. Photo: Argonne Nat
    ...

    Accident analysis and management Nuclear safety research CSNI Safety Safety research …
    Published date: 7 November 2022
    Joint project
    Component Operational Experience, Degradation and Ageing Programme (CODAP)

    Feeders on the Reactor Face in the Feeder Cabinet Photo: Canadian Nuclear Safety Commission (CNSC)

    The Component Operational Experience, Degradation and Ageing Programme (CODAP) combines the follow-u...

    Nuclear safety research LTO CSNI Safety of components and structures
    Published date: 21 October 2022
    Joint project
    Experiments on Source Term for Delayed Releases (ESTER) Project

    CHIP experimental facility to study fission product transport and deposition in the primary circuit. Photo: IRSN

    Following several years of experimental research in the field of source terms analysis...

    Accident analysis and management Nuclear safety research CSNI Joint project Accident management …
    Published date: 21 October 2022
    Joint project
    Analysis of Information from Reactor Building and Containment Vessel and Water Sampling in Fukushima Daiichi NPS (ARC-F) project

    Investigation for damage condition and radiation dose in Unit 3 at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (December 2019). Photo: Japan Nuclear Regulation Au...

    Fukushima Accident analysis and management Nuclear safety research Accident management
    Published date: 19 October 2022
    Joint project
    Cabri International Project (CIP)

    Cabri Reactor (Commissariat à l’énergie atomique et aux énergies alternatives)

    The Cabri International Project (CIP) began in March 2000 to study the behaviour of nuclear fuel rods and cladding durin...

    Fuel in nuclear safety Nuclear fuel Nuclear safety research CSNI
    Published date: 18 October 2022
    Joint project
    Fukushima Daiichi Nuclear Power Station Accident Information Collection and Evaluation (FACE) Project

    Appearance of Unit 1 and 2 reactor buildings at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (June 2022). Photo: Japan Nuclear Regulation Authority

    The FACE projec...

    Fukushima Accident analysis and management Nuclear safety research CSNI Joint project Accident management …
    Published date: 17 October 2022
    Joint project
    Halden Reactor Project - Fuels and Material

    The Halden Reactor Project has been in operation at the Institute for Energy Technology (IFE) in Norway since 1958 and is the oldest NEA joint project. It brings together a large international techni...

    Nuclear fuel Nuclear safety research LTO CSNI Joint project Safety of components and structures …
    Published date: 17 October 2022
    Joint project
    Dragon Project

    View of Dragon Reactor. Photo: AEA Technology.

    In 1959, twelve OECD countries began the Dragon Reactor Experiment (DRE) to build a reactor at Winfrith in Dorset, United Kingdom. The Dragon was the fi...

    Criticality safety Generation IV reactors Nuclear science Gas-cooled reactors Reactor physics …
    Published date: 14 October 2022
    Joint project
    Studsvik Material Integrity Life Extension (SMILE) Project

    Studsvik’s pool facility for storage and inspection of SMILE materials, left: 29 tonnes transportation flask, three pools each about 8 meters deep; and right: pool-in-pool for cutting and inspections...

    Long-term operation Nuclear safety research LTO Safety of components and structures
    Published date: 11 October 2022
    Joint project
    Loss of Forced Coolant (LOFC) Project

    JAEA  High-temperature Engineering Test Reactor Photo: Japan Atomic Energy Agency (JAEA)

     

    The Committee on the Safety of Nuclear Installations (CSNI) Task Group on Advanced Reactor Experimental Facil...

    Generation IV reactors Gas-cooled reactors Accident analysis and management Nuclear safety research CSNI …
    Published date: 11 October 2022
    Joint project
    QUENCH-ATF project

    Image: QUENCH facility at KIT. Court. KIT. 

    The purpose of the QUENCH-ATF project is to investigate the chemical, mechanical and thermal-hydraulics behaviour of ATF claddings in Design Basis Accident...

    Nuclear science Nuclear safety research Joint project Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 1 April 2022
    Joint project
    Thermal-hydraulics, Hydrogen, Aerosols and Iodine (THAI) Project

    The experimental investigations carried out in the frame of the THAI (2007-2009) and THAI-2 (2011-2014) projects contributed significantly to improve the understanding of hydrogen and fission-product...

    Fission products Accident analysis and management Thermal hydraulics Nuclear safety research Joint project Accident management …
    Published date: 18 February 2022
    Joint project
    Halden Human Technology Organisation (HTO) Project

    The Halden Reactor Project has been in operation since 1958 and is the oldest NEA joint project. It brings together an important international technical network in the area of nuclear safety ranging ...

    Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Safety research …
    Published date: 10 November 2021
    Joint project
    THAI Experiments on Mitigation measures, and source term issues to support analysis and further Improvement of Severe accident management measures (THEMIS) Project

    In the wake of the THAI project, conducted in three phases from 2007 until 2019, a new project, "THAI Experiments on Mitigation measures, and source term issues to support analysis and further Improv...

    Fission products Accident analysis and management Thermal hydraulics Nuclear safety research Joint project Accident management …
    Published date: 11 May 2021
    Joint project
    Thermochemical Database (TDB) Project

    The Thermochemical Database (TDB) Project develops a reference database of chemical thermodynamic values for elements and compounds relevant to the safety of radioactive waste repositories and vital ...

    Thermodynamics TDB Radioactive waste management Data Bank Thermochemical database Joint project Chemical thermodynamic series …
    Published date: 28 May 2020
    Joint project
    Sorption Project

    Sorption is a combination of physical and chemical processes by which the migration of radionuclides in the geosphere (and possibly from a radioactive waste repository) can be slowed down under certa...

    Sorption Project Thermodynamics Thermodynamic data Joint project
    Published date: 28 May 2020
    Joint project
    Bubbler Condenser Project

    There are several VVER-440/213* type nuclear power plants operating in the Czech Republic, Hungary, Slovak Republic, Russia and Ukraine. VVER-440/213 pressurised water reactors (PWRs) have a pressure...

    Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Joint project Safety of components and structures Accident management Pressurised water reactors Risk …
    Published date: 22 April 2020
    Joint project
    Computer-based Systems Important to Safety (COMPSIS) Project

    Software-based systems are used and retrofitted in operating nuclear power plants worldwide. The failure modes of both hardware and software in these systems are to some extent different from the ana...

    Risk assessment Accident analysis and management Digital instrumentation Nuclear safety research Safety research Digital instrumentation and control in nuclear safety …
    Published date: 22 April 2020
    Joint project
    Loss-of-fluid Test (LOFT) Project

    The Loss-of-fluid Test (LOFT) Research Programme was originally set up by the US Nuclear Regulatory Commission. Part of the programme was later broadened into an international collaboration project u...

    Risk assessment Accident analysis and management Verification and validation Fuel cycle facility safety Validation Nuclear safety research Safety of components and structures Codes and programs Safety research …
    Published date: 22 April 2020
    Joint project
    Melt Coolability and Concrete Interaction (MCCI) Project

    In a core melt accident, if the molten core is not retained in-vessel despite severe accident mitigation actions, the core debris will relocate to the reactor cavity region and interact with the stru...

    Risk assessment Light water reactors Accident analysis and management Fuel cycle facility safety Nuclear safety research Joint project Safety of components and structures Safety research …
    Published date: 22 April 2020
    Joint project
    Plant Safety Monitoring and Assessment System (PLASMA) Project

    Under an agreement with the Japan Atomic Energy Research Institute, (JAERI), the NEA supported an international research project with the goal of developing a plant safety monitoring and assessment s...

    Risk assessment Accident analysis and management Nuclear safety research Joint project Accident management Pressurised water reactors Safety research …
    Published date: 22 April 2020
    Joint project
    PSB-VVER Project

    The PSB-VVER is a large-scale thermal-hydraulics testing facility operated by the Electrogorsk Research and Engineering Centre (EREC) in Russia. The PSB-VVER Project was intended to provide the exper...

    Risk assessment Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Joint project Safety of components and structures Codes and programs Pressurised water reactors Safety research …
    Published date: 22 April 2020
    Joint project
    Material Scaling (MASCA) Project

    The Material Scaling (MASCA) Project was a follow-up of the RASPLAV Project and investigated in-vessel phenomena during a severe accident. Specifically, it addressed the influence of the chemical c...

    Risk assessment Accident analysis and management Nuclear safety research Joint project Safety of components and structures …
    Published date: 22 April 2020
    Joint project
    RASPLAV Project

    The RASPLAV* Project was regarded as a successor to the Three Mile Island Vessel Investigation Project (TMI-VIP) completed in 1993. The TMI-VIP Project was set up to examine and assess the conditio...

    Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures …
    Published date: 22 April 2020
    Joint project
    Sandia Lower Head Failure Project

    During a severe accident, the lower head of a reactor pressure vessel (RPV) can be subjected to significant thermal and pressure loads. The lower head has the potential to fail, releasing large amoun...

    Risk assessment Accident analysis and management Nuclear safety research Joint project Safety of components and structures …
    Published date: 21 April 2020
    Joint project
    Steam Explosion Resolution for Nuclear Applications (SERENA) Project

    The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Analysis and Management of Accidents (WGAMA) initiated a co-ordinated programme on Steam Explosion Resolution for Nuclear ...

    Risk assessment Accident analysis and management Information, data and knowledge management Nuclear safety research Ancillary data Safety of components and structures …
    Published date: 20 April 2020
    Joint project
    Three Mile Island Reactor Pressure Vessel Investigation Project (TMI-VIP)

    On 28 March 1979, a partial meltdown of the Three Mile Island unit 2 (TMI-2) reactor occurred at the TMI nuclear power plant near Harrisburg, Pennsylvania, United States.

    A TMI accident evaluation pr...

    Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety of components and structures …
    Published date: 20 April 2020
    Joint project
    OECD-IAEA Paks Fuel Project

    During a fuel crud removal operation on the Paks-2 unit on 10 April 2003, several fuel assemblies were severely damaged. The assemblies were being cleaned in a special tank of the Paks Nuclear Power ...

    Fuel in nuclear safety Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety of components and structures …
    Published date: 20 April 2020
    Joint project
    Piping Failure Data Exchange (OPDE) Project

    The goals of the Piping Failure Data Exchange (OPDE) Project were to:

    • collect and analyse piping failure event data to promote a better understanding of underlying causes, impact on operations and s...
    Nuclear safety research Joint project Safety of components and structures
    Published date: 17 April 2020
    Joint project
    Stress Corrosion Cracking and Cable Ageing Project (SCAP)

    The Stress Corrosion Cracking and Cable Ageing Project (SCAP) lasted four years (2006-2010). The project’s main objectives were to:

    • establish two complete databases with regard to major ageing pheno...
    Joint project
    Published date: 17 April 2020
    Joint project
    Cable Ageing Data and Knowledge (CADAK) Project

    In 2006, two subjects, stress corrosion cracking and the degradation of cable insulation were selected as the focus of the Stress Corrosion Cracking and Cable Ageing Project (SCAP). The project ran f...

    Nuclear safety research Joint project Safety of components and structures
    Published date: 17 April 2020
    Joint project
    SESAR Thermal-Hydraulics (SETH) Project

    The SESAR Thermal-hydraulics (SETH) Project began in 2001 and consisted of thermal-hydraulic experiments in support of accident management, which were carried out at facilities identified by the Comm...

    Thermal hydraulics
    Published date: 16 April 2020
    Joint project
    Rig-of-safety Assessment (ROSA) Project

    The Rig-of-safety Assessment (ROSA) Project aimed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety using the Japanese rig-of-safety assessment/large-scale...

    Risk assessment Accident analysis and management Thermal hydraulics Fuel cycle facility safety Nuclear safety research CSNI Safety Safety research …
    Published date: 8 April 2020
    Joint project
    Source Term Evaluation and Mitigation (STEM) Project

    On this page

    • STEM phases
      • First phase (2011-2015)
      • Second phase (2016-2019)

    STEM phases

    First phase (2011-2015)

    The STEM Project was initiated with a first phase in 2011 to improve the general ...

    Fuel in nuclear safety Risk assessment Accident analysis and management Nuclear safety research CSNI Safety Safety research …
    Published date: 8 April 2020
    Joint project
    Information System on Occupational Exposure (ISOE) Project

    The Information System on Occupational Exposure (ISOE) Project provides a forum for radiological protection (RP) professionals from nuclear electricity utilities and national regulatory authorities w...

    Published date: 6 April 2020
    Joint project
    Hydrogen Mitigation Experiments for Reactor Safety (HYMERES) Project

    On this page

    • HYMERES phases
      • First phase (2013-2016)
        • Facilities Description
      • Second phase (2017-2021)

    HYMERES phases

    First phase (2013-2016)

    The main objective of the first phase of the Hydro...

    Fuel in nuclear safety Risk assessment Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Safety Safety research …
    Published date: 6 April 2020
    Joint project
    High Energy Arcing Fault Events (HEAF) Project

    The HEAF Project was planned as a three-year programme to be conducted by the United States Nuclear Regulatory Commission (NRC) at a facility in the US. The project's aim was to conduct experiments i...

    Risk assessment Accident analysis and management Fuel cycle facility safety Safety of electrical systems Nuclear safety research CSNI Safety Safety research …
    Published date: 6 April 2020
    Joint project
    Fire Propagation in Elementary, Multi-room Scenarios (PRISME) Project

    The acronym PRISME comes from the French phrase propagation d’un incendie pour des scénarios multi-locaux élémentaires, which in English can be translated as "fire propagation in elementary, multi-ro...

    Fuel in nuclear safety Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety Safety research …
    Published date: 3 April 2020
    Joint project
    Fire Incidents Records Exchange (FIRE) Project

    The main purpose of the project is to encourage multilateral co-operation in the collection and analysis of data relating to fire events. The objectives of the NEA Fire Project are to:

    • collect fire ...
    Accident analysis and management Fuel cycle facility safety External hazards and nuclear safety Nuclear safety research Databases CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 3 April 2020
    Joint project
    Co-operative Programme for the Exchange of Scientific and Technical Information on Nuclear Installation Decommissioning Projects (CPD)

    The International Co-operative Programme for the Exchange of Scientific and Technical Information Concerning Nuclear Installation Decommissioning Projects (CPD) is a joint undertaking of a limited nu...

    Decommissioning Nuclear decommissioning Joint project
    Published date: 3 April 2020
    Joint project
    Behaviour of Iodine Project (BIP)

    The NEA Behaviour of Iodine Project (BIP) was created to provide separate effects and modelling studies of iodine behaviour in a nuclear reactor containment building following a severe accident. This...

    Fuel in nuclear safety Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety Safety of components and structures Accident management Safety research …
    Published date: 2 April 2020
    Joint project
    NEST project dedicated to advanced remote technology and robotics for decommissioning

    This NEST project led by JAEA/CLADS will be dedicated to advanced remote technology for decommissioning under intense gamma-ray radiation environments (e.g robotics, virtual reality).

    A short program...

    Decommissioning Nuclear Education, Skills and Technology (NEST) Framework Remote and robotic system
    Published date: 18 February 2020
    Joint project
    NEST Small Modular Reactors (SMRs)

    This NEST project aims to integrate SMR research projects from the individual Participating Organisation countries into a broader and more impactful programme. It will include elements of technology ...

    Reactor physics Nuclear Education, Skills and Technology (NEST) Framework Spent fuel Reactor design
    Published date: 18 February 2020
    Joint project
    NEST Hydrogen Containment Experiments for Reactor Safety (HYMERES) Project

    NEST HYMERES (Hydrogen containment experiments for reactor safety) project is addressing safety relevant phenomena in containments during accidents. It offers hands-on training opportunity during the...

    Nuclear Education, Skills and Technology (NEST) Framework Reactor design
    Published date: 6 December 2019
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