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    Reactor physics
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    Event
    SERPENT-2 bootcamp for beginners
    14 - 17 November 2023
    NEA, Paris, France

    Date: 14-17 November 2023

    Place: NEA Headquarters
                46, Quai Alphonse Le Gallo
                92100 Boulogne-Billancourt (Paris) - FRANCE
    Minimum enrollment: 12 participants
    Maximum enrollment: 20 participants...
    Reactor physics Multi-physics simulations Monte Carlo method Radiation shielding Data Bank Training …
    Published date: 2 October 2023
    Event
    NJOY Training Course
    4 - 7 December 2023
    NEA, Paris, France
    Date: 4-7 December 2023
    Place: OECD/NEA Headquarters
                46, Quai Alphonse Le Gallo
                92100 Boulogne-Billancourt (Paris) - FRANCE
    Minimum enrollment: 15 participants
    Maximum enrollment: 20 partici...
    CPS Codes and programs Reactor physics Data Bank Training Nuclear data processing ENDF …
    Published date: 8 September 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
    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
    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
    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
    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
    Event
    SCALE TRITON Lattice Physics and Depletion
    22 - 26 May 2023
    NEA, Paris (France)
    Place: OECD/NEA Headquarters in Paris, France
    Minimum enrollment required: 12 participants
    Course fee: 2300 EUR
    Registration closed
     
    The training course will be taught in English.
    Participan...
    Modelling and simulation Reactor physics CPS Data Bank Uncertainty analysis Training …
    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 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
    Activity
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM)

    The goal of the Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM) is to determine the uncertainty in light wate...

    Modelling and simulation Reactor physics Light water reactors Verification and validation Validation Uncertainty quantification Uncertainty analysis Benchmark Reactor physics Pressurised water reactors …
    Published date: 25 April 2023
    News
    Scientific issues of nuclear reactor systems

    NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 19-21 February 2020.

    Reactor physics News brief Nuclear science SINBAD Reactor physics …
    Published date: 4 March 2020
    News
    Scientific issues and uncertainty analysis of nuclear reactor systems

    NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 15-19 February 2021.

    Reactor physics News brief Nuclear science EGPRS SINBAD WPRS Reactor physics …
    Published date: 24 February 2021
    News
    Enhancing the NEA Shielding Integral Benchmark Archive and Database (SINBAD)

    EGPRS Task Force members met on 3 April 2023.

    Reactor physics News brief NSC Nuclear science Radiation shielding EGPRS SINBAD WPRS Reactor physics …
    Published date: 7 April 2023
    Activity
    Expert Group on Reactor Fuel Performance (EGRFP)

    Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) the expert group performs specific tasks associated with fuel performance aspects of pr...

    Nuclear fuel Reactor physics EGRFP Reactor physics
    Published date: 8 March 2023
    Subtopic
    Reactor fuel performance

    Understanding fuel performance is a key condition for successful reactor operation. Scientific knowledge in this domain was conceived by experimental tests encoded into software routines to ensure ac...

    Reactor physics Fuel studies Nuclear science Reactor physics
    Published date: 10 December 2020
    Subtopic
    Reactor physics

    Questions relating to the space, time end energy distribution of neutrons and radiation in different media are the domain of reactor physics.

    Reactor physics Verification and validation Fast reactor Benchmark Advanced reactors Reactor physics …
    Published date: 2 December 2019
    NEA Document
    Existing Practices for Multi-physics Validation: Report on Sub-Task 3, Task Force 2
    NEA/NSC/R(2019)7

    The modelling and simulation of nuclear systems allow scientists and engineers to probe aspects of the operation of these systems beyond what has been precisely measured. This has numerous applicatio...

    Reactor physics Nuclear science WPRS Multiphysics Nuclear science Benchmark Reactor physics Multiphysics EGMUP …
    Published date: 11 October 2022
    NEA Document
    Burn-up Credit Criticality Studies: Benchmark Analyses for Pressurised Water Reactors
    NEA/NSC/R(2016)1
    English Nuclear science Criticality WPNCS WPRS Multiphysics Reactor physics Multiphysics EGMUP Reactor physics Criticality safety NSC Nuclear science …
    Published date: 23 February 2016
    Subtopic
    Thermal hydraulics and mechanics

    Thermal hydraulics and mechanics deals with the physics and mechanics of the flow and energetic transfer of liquids, and its interactions with the structures around them in large complex systems, suc...

    Reactor physics Nuclear science Thermal hydraulics Verification and validation Verification Validation Benchmark Thermal hydraulics and mechanics Reactor physics …
    Published date: 10 December 2020
    NEA Document
    Benchmark for Neutronic Analysis of Sodium-cooled Fast Reactor Cores with Various Fuel Types and Core Sizes
    NEA/NSC/R(2015)9

    Sodium fast reactors offer the most promising type of reactors to achieve such Generation IV goals at a reasonable time scale given the experience accumulated over the years. However, it is recognise...

    English Nuclear fuel Fuel studies Generation IV reactors Nuclear science WPRS Reactor physics Reactor physics Sodium-cooled reactor NSC EGPRS Nuclear science Benchmark …
    Published date: 5 November 2015
    NEA Document
    International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests - Volume II: Benchmark results of phase I Void distribution
    NEA/NSC/R(2015)4

    The objective of the benchmark was twofold. First, the benchmark aimed to evaluate currently available computational approaches in an effort to understand the strengths and weaknesses of current ther...

    English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Nuclear science Benchmark …
    Published date: 24 June 2015
    NEA Document
    International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests - Volume III: Departure from nucleate boiling
    NEA/NSC/R(2015)7

    The need to refine models for best-estimate calculations based on good-quality experimental data has arisen for various nuclear applications. One of the most extensive and valuable databases availabl...

    English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Nuclear science Benchmark Pressurised water reactors …
    Published date: 2 October 2015
    NEA Document
    MOx Depletion Calculation Benchmark
    NEA/NSC/R(2016)3

    In 2013, the Expert Group on Reactor Physics and Advanced Nuclear Systems (EGRPANS) published a report that investigated fuel depletion effects in a pressurised water reactor (PWR). This was entitled...

    English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science Reactor physics …
    Published date: 14 June 2016
    NEA Document
    NEA Benchmark of the Modular High-Temperature Gas-Cooled Reactor 350 MW Core DesignVolumes I and II
    NEA/NSC/R(2017)4
    English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science EGTHM Reactor physics EGMUP …
    Published date: 6 December 2017
    NEA Document
    A Code to Code Benchmark for High-Temperature Gas-Cooled Reactor Fuel Element Depletion
    NEA/NSC/R(2019)1

    The high-temperature gas-cooled reactor (HTGR) is a Generation IV reactor concept that uses a graphitemoderated gas-cooled nuclear reactor with a once-through uranium fuel cycle. This design permits ...

    English Nuclear fuel Fuel studies Generation IV reactors Nuclear science WPRS Reactor physics Multiphysics EGMUP Reactor physics Cogeneration NSC Gas-cooled reactors EGPRS Nuclear science Benchmark …
    Published date: 18 January 2019
    NEA Document
    Coupled Neutronic/Thermal-Fluid Benchmark of the MHTGR-350 MW Core Design: Results for Phase I Exercise 1
    NEA/NSC/R(2019)5
    Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science EGTHM Reactor physics EGMUP …
    Published date: 12 October 2020
    NEA Document
    Coupled Neutronic/Thermal-Fluid Benchmark of the MHTGR-350 MW Core Design: Results for the Lattice Physics Exercises
    NEA/NSC/R(2019)6

    The purpose of this prismatic High Temperature Reactor (HTR) benchmark is to provide a solution set that can be used in future code benchmarking and to better understand the effects induced by the pr...

    English Nuclear science WPRS Multiphysics EGTHM Reactor physics Multiphysics EGMUP Reactor physics NSC EGPRS Nuclear science …
    Published date: 18 November 2021
    NEA Document
    Benchmark Specifications for the Fluoride-salt High-temperature Reactor (FHR) Reactor Physics Calculations
    NEA/NSC/R(2020)5

    This benchmark focuses on FHR reactors with plates and triso fuel. Several phases are planned, starting with neutronics on a simple fuel element simulation without burn-up, and gradually extending to...

    Reactor physics Nuclear science EGPRS Verification WPRS Nuclear science Reactor physics …
    Published date: 4 June 2021
    NEA Document
    NUPEC BWR Full-size Fine-mesh Bundle Test BFBT Benchmark - Volume III: Results of Phase I on Void Distribution
    NEA/NSC/R(2020)6

    In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for Boiling Water Reactor (BWR) fuel bundles. This international benchmark, bas...

    English Boiling water reactors Nuclear science Nuclear safety WPRS Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics Nuclear science Benchmark …
    Published date: 1 June 2021
    NEA Document
    NUPEC BWR Full-size Fine-mesh Bundle Test BFBT Benchmark - Volume IV: Results of Phase II on Pressure Drop and Critical Power
    NEA/NSC/R(2020)7

    In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for boiling water reactor (BWR) fuel bundles. This international benchmark, bas...

    English Boiling water reactors Nuclear science Nuclear safety WPRS EGTHM Reactor physics Reactor physics Nuclear science Benchmark …
    Published date: 2 December 2021
    Publications and Reports
    VVER-1000 Coolant Transient Benchmark - Phase 1 Phase I (V1000CT-1), Volume 3: Summary Results of Exercise 2 on Coupled 3-D Kinetics/Core Thermal-hydraulics

    In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...

    English Reactor physics Nuclear science WPRS Multiphysics Nuclear science Reactor physics Multiphysics EGMUP …
    Published date: 16 November 2007
    Publications and Reports
    VVER-1000 Coolant Transient Benchmark - Phase 2 (V1000CT-2): Summary Results of Exercise 1 on Vessel Mixing Simulation

    Recently developed best-estimate computer code systems for modelling 3-D coupled neutronics/thermal-hydraulics transients in nuclear reactors need to be validated against results from experiments and...

    English Reactor physics Nuclear science WPRS Multiphysics Nuclear science Reactor physics Multiphysics EGMUP …
    Published date: 5 October 2010
    NEA Document
    PBMR Coupled Neutronics/Thermal-Hydraulics Transient Benchmark: The PBMR-400 Core Design - Volume 1: The Benchmark Definition
    NEA/NSC/DOC(2013)10

    This report defines the “OECD/NEA/NSC PBMR Coupled Neutronics/Thermal-hydraulics Transient Benchmark of the PBMR-400 Core Design”. This chapter gives more information on the day-to-day management of ...

    English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics Reactor physics Multiphysics EGMUP Modelling and simulation Reactor physics NSC Thermal hydraulics Nuclear science Benchmark …
    Published date: 19 June 2013
    NEA Document
    OECD/NRC Benchmark Based on NUPEC Pressurised Water Reactor Sub-channel and Bundle Tests (PSBT) - Volume I: Experimental database and final problem specifications
    NEA/NSC/DOC(2012)1

    Based on the success of the OECD/NRC BFBT Benchmark, Japan released data based on the NUPEC PWR Sub-channel and Bundle Tests (PSBT) Benchmark and asked Pennsylvania State University (PSU) in the Unit...

    English Nuclear science WPRS Multiphysics EGTHM Reactor physics Multiphysics Reactor physics NSC Nuclear science Benchmark Pressurised water reactors …
    Published date: 4 January 2012
    NEA Document
    Benchmarks for Uncertainty Analysis in Modelling (UAM) for the Design, Operation and Safety Analysis of LWRs - Volume I: Specification and Support Data for Neutronics Cases (Phase I)
    NEA/NSC/DOC(2013)7
    English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science Reactor physics …
    Published date: 16 May 2013
    Publications and Reports
    NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark - Volume II: Uncertainty and Sensitivity Analyses of Void Distribution and Critical Power - Specification

    This report provides the specification for the uncertainty exercises of the international OECD/NEA, NRC and NUPEC BFBT benchmark problem including the elemental task. The specification was prepared j...

    English Nuclear science Light water reactors WPRS Thermal hydraulics and mechanics EGTHM Reactor physics Modelling and simulation Reactor physics Verification and validation Validation Uncertainty analysis Nuclear science Benchmark …
    Published date: 1 January 2010
    NEA Document
    Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-14)
    NEA/NSC/R(2021)2

    Proceedings of the Fourteenth Workshop, 30 October-2 November 2018, Gyeongju, Korea.

    English Nuclear science Radiation shielding WPRS Proceedings Reactor physics Reactor physics NSC EGPRS Nuclear science …
    Published date: 16 December 2021
    NEA Document
    Shielding Aspects of Accelerators, Target and Irradiation Facilities (SATIF-13) - Proceedings of the Thirteenth Meeting, 10-12 October 2016, Dresden, Germany
    NEA/NSC/R(2018)2
    English Reactor physics NSC Nuclear science Radiation shielding EGPRS WPRS Nuclear science Proceedings Reactor physics …
    Published date: 8 December 2021
    NEA Document
    Shielding Aspects of Accelerators, Target and Irradiation Facilities (SATIF-12)
    NEA/NSC/R(2015)3

    Twelfth Workshop Proceedings, Batavia, Illinois, United States, 28-30 April 2014

    English Reactor physics NSC Nuclear science Radiation shielding EGPRS WPRS Nuclear science Proceedings Reactor physics …
    Published date: 2 June 2015
    Publications and Reports
    Review of Integral Experiments for Minor Actinide Management

    Spent nuclear fuel contains minor actinides (MAs) such as neptunium, americium and curium, which require careful management. This becomes even more important when mixed oxide (MOX) fuel is being used...

    English Reactor physics Nuclear science EGPRS WPRS Nuclear science …
    Published date: 17 February 2015
    Publications and Reports
    NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark

    Refined models for best-estimate calculations based on good-quality experimental data can improve the understanding of phenomena and the quantification of margins for operating nuclear power reactors...

    English Reactor physics Nuclear science Multiphysics Nuclear science Benchmark Reactor physics Multiphysics …
    Published date: 7 July 2006
    Publications and Reports
    VVER-1000 MOX Core Computational Benchmark

    The United States and the Russian Federation have each agreed to dispose of 34 tonnes of weapons-grade plutonium that are beyond their defence needs. One effective way to dispose of this plutonium is...

    English Modelling and simulation Reactor physics Nuclear science Nuclear science Benchmark Pressurised water reactors …
    Published date: 20 January 2006
    Publications and Reports
    Very High Burn-ups in Light Water Reactors

    Average fuel burn-up in light water reactors (LWRs) has steadily increased with time as technological advances have been made. The practical limit is currently in the region of 50 GWd/t. The main dri...

    English Nuclear fuel Reactor physics Fuel studies Nuclear science Light water reactors Nuclear science Reactor physics …
    Published date: 22 August 2006
    NEA Document
    Overview of SMORN-VI: Summary of the Sixth Symposium on Reactor Noise (SMORN VI)
    NEA/NEACRP/L(1991)333

    A summary of the Sixth Symposium on Reactor Noise (SMORN VI), Gatlinburg, United States, 19-24 May 1991

    English Reactor physics NSC Nuclear science Nuclear science …
    Published date: 1 January 1991
    NEA Document
    VENUS-1 Two-Dimensional Benchmark on Ex-Core Dosimetry Computations
    NEA/NSC/DOC(1996)25

    In this benchmark exercise the goal is to test the current state-of-the-art two-dimensional methods of calculating neutron flux to reactor components against the measured data of the VENUS-1 critical...

    English Reactor physics NSC Nuclear science Nuclear science Benchmark Reactor physics …
    Published date: 1 January 1996
    NEA Document
    Computing Radiation Dose to Reactor Pressure Vessel and Internals: State-of-the-Art Report
    NEA/NSC/DOC(1996)5

    The OECD/NEA Nuclear Science Committee Task Force on Computing Radiation Dose and Modelling of Radiation-induced Degradation of Reactor Components was set up in November 1995 in response to a request...

    English Reactor physics NSC Radiation shielding Radiation Nuclear science Radiation safety Radiation transport and shielding Reactor physics …
    Published date: 1 January 1996
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