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    Publications and Reports
    Specifications for the Generalised Nuclear Database Structure Version 2.0

    Knowledge of basic nuclear physics data is essential for the modelling and safe operation of all types of nuclear facilities. The de facto international standard format, Evaluated Nuclear Data File 6...

    English WPEC Nuclear science Nuclear science Nuclear data processing …
    Published date: 22 September 2023
    NEA Document
    Benchmark on Dose Rate Calculations for Irradiated Assembly
    NEA/NSC/R(2023)8

    The Task Force on Dose Rate Calculations for Irradiated Fuel Assembly was launched in 2015 to assess code predictions of dose rates from bare spent fuel assemblies and to benchmark multiple codes and...

    WPFC Nuclear science Spent fuel Nuclear science Benchmark …
    Published date: 19 September 2023
    NEA Document
    Experimental Needs for Criticality Safety Purposes
    NEA/NSC/R(2022)6

    The goal of the Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS) Subgroup on Experimental Needs for Criticality Safety Purposes (SG-5) was to highlight the needs of int...

    Criticality safety Nuclear science Criticality WPNCS Experimental needs Nuclear science …
    Published date: 15 September 2023
    Activity
    Nuclear Education, Skills and Technology (NEST) Framework

    The NEA launched the Nuclear Education, Skills and Technology (NEST) Framework in partnership with its member countries to help address important gaps in nuclear skills capacity building, knowledge t...

    Nuclear science Education Nuclear Education, Skills and Technology (NEST) Framework Human resources development (HRD) International co-operation Training Nuclear knowledge management …
    Published date: 13 September 2023
    Activity
    Burn-up credit and nuclear criticality safety

    Burn-up credit is a safety approach that accounts for the reduction in the reactivity of configurations with spent nuclear fuel due to the change in their composition after irradiation.

    Criticality safety NSC Nuclear science Criticality WPNCS …
    Published date: 11 September 2023
    Event
    TCOFF-II call for R&D proposals
    6 September 2023 - 27 October 2023

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

    Nuclear science Thermodynamics Thermodynamic data TCOFF Nuclear science Joint project …
    Published date: 5 September 2023
    Event
    Materials Modelling and Simulation for Nuclear Fuel (MMSNF) Workshop 2023
    28 - 30 November 2023
    McMaster University, Hamilton, ON (Canada)

    The Materials Modelling and Simulation for Nuclear Fuels (MMSNF) Workshop is a forum for the discussion of state-of-the-art modelling and simulation techniques for nuclear fuels and cladding material...

    Material science Nuclear science Materials science WPFM Nuclear science …
    Published date: 1 September 2023
    NEA Document
    Burnup Credit Criticality Benchmark Phase IIID: Burnup Calculations of Gadolinium- Bearing Fuel Rods in Boiling Water Reactor Assemblies for Storage and Transportation
    NEA/NSC/R(2022)3/CORR

    Please note that this report was initially published in November 2022 (NEA/NSC/R(2022)3) under erroneous benchmark number IIB; in this updated version (NEA/NSC/R(2022)3/CORR) this has been corrected ...

    Criticality safety Nuclear science WPNCS Nuclear science Benchmark …
    Published date: 30 November 2022
    Event
    International School on Simulation of Nuclear Reactor Systems (SINUS)
    1 - 23 May 2023
    Online training & in-person event on 22-23 May 2023 in Bologna, Italy

    The NEA organised the first International School on Simulation of Nuclear Reactor Systems (SINUS) on the topic of Reactor single- and multi-physics simulations based on Light Water Reactor (LWR) Unce...

    Nuclear science Education WPRS Nuclear science Reactor physics …
    Published date: 4 May 2023
    Joint project
    Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression (TCOFF)

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

    TCOFF Phases

    First Phase (2017-2020)

    The Thermodynamic Characterisation of Fuel Debris and Fission Products ...

    Nuclear science Fission products Fukushima Thermodynamic data Nuclear safety research Safety research …
    Published date: 31 August 2023
    Activity
    WPFC Expert Group on Fuel Recycling and Waste Technology (EGFRW)

    Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Fuel Recycling and Waste Technology (EGFRW) focuses on the separation processes releva...

    Nuclear fuel WPFC EGFRC Fuel studies NSC Nuclear science Partitioning and transmutation EGFRW Fuel cycle physics and chemistry …
    Published date: 28 August 2023
    Activity
    WPFC Expert Group on Advanced Fuel Cycle Scenarios (EGAFCS)

    Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Advanced Fuel Cycle Scenarios (EGAFCS) studies the needs associated with the transitio...

    Nuclear fuel WPFC Fuel studies NSC Nuclear science EGAFCS Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 28 August 2023
    Activity
    WPFC Expert Group on Innovative Fuel Elements (EGIFE)

    Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Innovative Fuel Elements (EGIFE) conducts joint and comparative studies to identify te...

    Nuclear fuel WPFC Fuel studies NSC EGIFE Nuclear science EGIF Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 28 August 2023
    Activity
    WPFC Expert Group on Reactor Coolants/Components Technology (EGCoCoT)

    Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Reactor Coolants and Components Technology (EGCoCoT) undertakes activities to collect,...

    Nuclear fuel WPFC EGLM Fuel studies NSC Nuclear science EGCoCoT Liquid metal reactors Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 28 August 2023
    Activity
    Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC)

    The Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) studies advanced nuclear fuel cycles, including fuel cycle scenarios, innovative fuels and materials, separation chemistry, waste...

    Nuclear fuel WPFC Fuel studies NSC Nuclear science Liquid metal reactors Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 28 August 2023
    Activity
    Working Party on International Nuclear Data Evaluation Co-operation (WPEC)

    The NEA's nuclear data evaluation co-operation activities involve the following evaluation projects: ENDF (United States), JENDL (Japan), ROSFOND/BROND (Russia), JEFF (other Data Bank member countrie...

    NSC Nuclear science Nuclear data
    Published date: 28 August 2023
    Joint project
    Thermodynamics of Advanced Fuels - International Database (TAF-ID)

    On this page

    • TAF-ID Project
    • TAF-ID database: working and public versions
    • Goals of the TAF-ID project phases
    • Why is thermodynamic data for analyses involving nuclear fuel needed?
    • How is thermodynami...
    Material science Structural materials Fuel studies Nuclear science Materials science Thermodynamic data TAF-ID …
    Published date: 2 August 2023
    Event
    16th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (16IEMPT)
    24 - 27 October 2023
    NEA Headquarters, Boulogne-Billancourt, France

    The NEA is organising the 16th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (16IEMPT) on 24-27 October 2023. The meeting will be held at the NEA offices...

    Nuclear fuel WPFC Fission products Chemistry Actinides Advanced reactors Minor actinides NSC Back-end Nuclear fuel cycle Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 27 July 2023
    News
    The demise of zero power reactors: Addressing reduced experimental capabilities

    The NEA workshop gathered experts to discuss the challenges and opportunities related to the demise of zero power reactors.

    NSC Nuclear science WPRS Nuclear science
    Published date: 4 July 2023
    News
    Experts gather to discuss nuclear criticality safety

    The NEA Working Party on Nuclear Criticality Safety (WPNCS) held its bi-annual meetings in June 2023

    News brief Criticality safety Fuel studies Nuclear science Criticality WPNCS Benchmark …
    Published date: 24 July 2023
    News
    Training FISPACT-II users

    Co-organised with the UK Atomic Energy Authority, the course took place on 20-22 June 2023.

    News brief Nuclear science CPS Data Bank Nuclear science Training Codes and programs …
    Published date: 24 July 2023
    Activity
    Thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H)

    High-temperature gas-cooled nuclear reactors are one of the next generation reactor designs. This benchmark consists of a multi-staged code-to-code-to-data thermal hydraulics code validation benchmar...

    Thermal hydraulics Verification and validation Verification Validation Benchmark Reactor physics …
    Published date: 19 July 2023
    Activity
    Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)

    The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nu...

    Nuclear fuel Reactor physics Multi-physics simulations Fuel studies Light water reactors Thermal hydraulics WPRS Pressurised heavy water reactors Reactor physics Multiphysics …
    Published date: 18 July 2023
    Event
    21st Meeting of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)
    19 - 23 February 2024
    NEA headquarters (46, quai Alphonse Le Gallo, 92100 Boulogne-Billancourt, France)

    Under the guidance of the Nuclear Science Committee (NSC), the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, an...

    Nuclear science EGRFP EGRRS WPRS Multiphysics Radiation transport and shielding Thermal hydraulics and mechanics EGTHM Reactor physics Reactor fuel performance EGMUP NSC Nuclear science …
    Published date: 18 July 2023
    Event
    Sixteenth Workshop on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-16)
    28 - 31 May 2024
    INFN Laboratori Nazionali di Frascati, Frascati, Italy

    The Sixteenth Workshop on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-16) will take place on 28-31 May 2024 at the National Laboratories of Frascati of the Italian Na...

    Radiation shielding Nuclear science Radiation transport and shielding Co-sponsored event
    Published date: 18 July 2023
    News
    Improving thermodynamic databases and materials modelling for the analysis of severe accidents

    TCOFF-2 members discuss future activities.

    Thermodynamic data TCOFF Nuclear science Joint project Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 10 July 2023
    Event
    The demise of zero power reactors: From concern to action
    22 - 23 June 2023
    IRSN, Fontenay-aux-Roses, France

    In the early decades of nuclear reactor development, many countries built and operated zero-power facilities in which many different critical arrangements of materials were studied. These flexible ex...

    NSC Nuclear science WPRS Nuclear science
    Published date: 6 June 2023
    NEA Document
    State-of-the-Art Report on Multi-scale Modelling Methods
    NEA/NSC/R(2019)2
    Material science NSC Nuclear science Materials science Nuclear science …
    Published date: 29 September 2020
    News
    Benchmarking state-of-the art nuclear reactor simulations

    The annual WPRS Benchmarks Workshops took place on 22-26 May 2023 in Bologna, Italy.

    Reactor physics Nuclear science WPRS Multiphysics Nuclear science Benchmark Thermal hydraulics and mechanics Reactor physics Reactor fuel performance Multiphysics …
    Published date: 13 June 2023
    News
    Strategic use of nuclear fuel and materials research facilities – a pioneering output of the FIDES-II Framework

    10-year FIDES-II strategic plan will define key research needs in a variety of technical disciplines.

    Fuel in nuclear safety Nuclear fuel Nuclear science Nuclear safety FIDES Nuclear safety research Reactor fuel performance Nuclear science Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 19 June 2023
    News
    Challenging state-of-the art thermal hydraulics simulation capabilities for high temperature gas-cooled reactors

    Kick-off workshop of the thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using High Temperature Test Facility (HTTF) data.

    News brief Nuclear science WPRS Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Thermal hydraulics Nuclear science Benchmark …
    Published date: 16 June 2023
    News
    Training the next generation of nuclear simulation specialists

    The first International School on Simulation of Nuclear Reactor Systems (SINUS) took place on 22-23 May 2023.

    Reactor physics News brief Nuclear science Education WPRS Nuclear science Reactor physics …
    Published date: 14 June 2023
    News
    Advancing the understanding of materials science issues in nuclear fuels and structural materials

    WPFM held meetings on 23-25 May 2023.

    Material science Modelling and simulation News brief Nuclear science Materials science WPFM Nuclear science …
    Published date: 13 June 2023
    Activity
    FIDES-II Cross-Cutting Pillars

    The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues. 

    Fuel in nuclear safety Nuclear science Nuclear safety research Reactor fuel performance
    Published date: 13 June 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: 13 June 2023
    Activity
    Lead-cooled Fast Reactor Benchmark (LFR)

    Lead-cooled Fast Reactors (LFR) are rather new concepts which have gathered increasing international attention after the Generation-IV International Forum (GIF) selected them as promising candidates ...

    Generation IV reactors Verification and validation Verification Validation Liquid metal reactors Benchmark Reactor physics …
    Published date: 9 June 2023
    Activity
    Expert Group on Reactor Core Thermal-Hydraulics and Mechanics (EGTHM)

    Created in 2019, under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS) the expert group will perform specific tasks associated with core thermal-hydraulics aspects of...

    Reactor physics Sodium-cooled reactor Molten salt reactors Light water reactors Thermal hydraulics WPRS Reactor physics …
    Published date: 8 June 2023
    Activity
    Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM)

    Under the guidance of the Nuclear Science Committee (NSC), the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM) addresses materials science aspects of nuclea...

    Nuclear fuel Material science Structural materials NSC Nuclear science Materials science WPFM Nuclear science Accident tolerant fuels …
    Published date: 1 June 2023
    Subtopic
    Education and capacity building

    Sustained performance of nuclear technology depends on access to a talented and well-qualified workforce, thus it is important to ensure that adequate infrastructures exist for education and training...

    Nuclear science Education Training
    Published date: 22 July 2020
    Activity
    Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM)

    The Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) was formed to check the use of best-estimate codes and data....

    Sodium-cooled reactor Verification Fast reactor Benchmark Reactor physics …
    Published date: 24 May 2023
    Activity
    NEA Global Forum on Nuclear Education, Science, Technology and Policy

    The Global Forum on Nuclear Education, Science, Technology and Policy acts as an inclusive network of experts in the nuclear energy sector, primarily from academia, focused on enabling the generation...

    Nuclear science Education Human resources development (HRD) International co-operation Training Nuclear knowledge management …
    Published date: 24 May 2023
    Event
    WPRS Benchmarks Workshop 2023
    22 - 26 May 2023
    Zanhotel Europa, Via Cesare Boldini 11, Bologna, Italy + virtual option on ZOOM

    The annual Benchmark Workshops of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems will be hosted by the Italian National Agency for New Technologies, Energy and Sus...

    Reactor physics Nuclear science Multiphysics Nuclear science Benchmark Thermal hydraulics and mechanics Reactor physics Reactor fuel performance Multiphysics …
    Published date: 17 May 2023
    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: 17 May 2023
    Activity
    Nuclear Science Committee (NSC)

    The NEA nuclear science programme is developed and executed by the Nuclear Science Committee (NSC), comprising high-level scientific experts from all NEA member countries.

    Nuclear fuel Reactor physics Nuclear science Criticality Materials science Chemistry …
    Published date: 15 May 2023
    NEA Document
    Benchmark Study on Innovative Fuels for Fast Reactors with Fuel Performance Codes
    NEA/NSC/R(2022)5

    This report presents the results of a benchmark study on innovative fuels for fast reactors using fuel performance codes. Irradiation results were shared among participants of the expert group and co...

    WPFC Fuel studies NSC Nuclear science Nuclear science Benchmark Reactor fuel performance Fuel cycle physics and chemistry …
    Published date: 3 April 2023
    NEA Document
    Statistical Tests for Diagnosing Fission Source Convergence and Undersampling in Monte Carlo Criticality Calculations
    NEA/NSC/R(2021)3

    Monte Carlo criticality calculations involve a two-step procedure based on a stochastic implementation of the power iteration method: first, achieve convergence of the fission source distribution dur...

    Criticality safety Monte Carlo method NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 17 February 2023
    NEA Document
    Benchmark for Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Light Water Reactors: Volume I. Neutronics Phase (Phase I)
    NEA/NSC/R(2021)5

    Since the early 2000s there is an increasing demand from nuclear research, industry, safety and regulation for best-estimate predictions to be provided with their confidence bounds. Consequently, an ...

    Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science Benchmark …
    Published date: 18 April 2023
    Event
    International workshop on thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H)
    5 - 6 June 2023
    Oregon State University, Corvallis, Oregon, United States

    The NEA thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H), supervised by the Expert Group on Reactor Core Thermal-Hydraulics and Mechanic...

    Nuclear science Thermal hydraulics and mechanics Reactor physics Reactor physics NSC Thermal hydraulics Verification and validation Verification Validation Benchmark …
    Published date: 20 April 2023
    News
    ICSBEP and IRPhEP Technical Review Group meetings

    The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.

    News brief Nuclear science Criticality ICSBEP IRPhEP Reactor physics Reactor physics Criticality safety NSC SINBAD Nuclear science Benchmark …
    Published date: 24 April 2023
    News
    Members of NEA Second Framework for Irradiation Experiments (FIDES-II) meet in Czech Republic

    Members of FIDES-II from 12 countries assembled in Prague, Czech Republic, on 17-21 April 2023 for meetings of its Technical Advisory Group and Governing Board.

    Fuel in nuclear safety Nuclear fuel News brief Nuclear science Nuclear safety FIDES Reactor fuel performance NSC Nuclear science Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 21 April 2023
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