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    NEA Working Paper
    Thermal-hydraulic Code Validation Benchmark Specifications for High -temperature Gas-cooled Reactors (HTGR) using High-temperature Test Facility (HTTF) data
    NEA/WKP(2024)3

    In 2022, the WPRS Expert Group on Thermal Hydraulics and Mechanics (EGTHM) mandated a new benchmark on high-temperature gas-cooled reactors (HTGR) using high-temperature test facility (HTTF) data an...

    CFD Nuclear science Thermal hydraulics WPRS Nuclear science Benchmark EGTHM …
    Published date: 28 April 2025
    NEA Document
    Summary Report of the 16th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (16IEMPT)
    NEA/NSC/R(2024)2

    Efforts to enhance the safety, sustainability and economic efficiency of nuclear energy are driving international research into advanced nuclear fuel cycles. A key component of these efforts is parti...

    Nuclear science Nuclear fuel cycle Partitioning and transmutation
    Published date: 11 April 2025
    NEA Document
    BWR Severe Accident Mitigation Guidelines (SAMG) Information Compilation and Reactor Water Level Measurement
    NEA/CNRA/R(2022)2

    This report presents nuclear plant operator and regulatory practices in the area of severe accident management (SAM) in general and more specifically the regulation of its severe accident mitigation ...

    Boiling water reactors Boiling water reactors and nuclear safety CNRA Nuclear safety WPBWR Safety assessment Nuclear safety regulation Accident management …
    Published date: 8 April 2025
    NEA Document
    Consensus Position on Regulatory Inspections of Digital Instrumentation and Control Systems and Components Important to Safety Used at Nuclear Power Plants (CP-15)
    NEA/CNRA/R(2022)3

    Regulatory inspections of digital instrumentation and control (I&C) hardware and software for systems and components important to safety at nuclear power plants are needed to verify that such systems...

    CNRA Nuclear safety Digital instrumentation WGDIC Safety Digital instrumentation and control in nuclear safety …
    Published date: 8 April 2025
    NEA Document
    ICDE Project report: Lessons learnt from common-cause failures of motor-operated valves
    NEA/CSNI/R(2021)7

    This report presents a study performed on a set of common cause failure (CCF) events of motor operated valves (MOV) within the International Common Cause Failure Data Exchange (ICDE) project. In July...

    Nuclear safety Nuclear safety research CSNI PRG Databases CSNI Joint project Safety …
    Published date: 7 April 2025
    NEA Document
    ICDE Topical Report Operational Experience on Common-Cause Failures due to External Environmental Factors
    NEA/CSNI/R(2020)15

    This report presents a study performed on a set of common-cause failure (CCF) events within the International Common-cause failure Data Exchange (ICDE) project. The topic of the study was external fa...

    Nuclear safety Nuclear technology Nuclear safety research CSNI PRG Databases CSNI Joint project Safety Safety research …
    Published date: 4 April 2025
    NEA Document
    Consensus Position on the Qualification of Existing and New Material Manufacturing Techniques within Codes and Standards
    NEA/CNRA/R(2023)3

    The Nuclear Energy Agency (NEA) Working Group on Codes and Standards (WGCS) has agreed that a consensus position on the topic of the qualification of existing and new material man facturing technique...

    WGCS CNRA Nuclear safety Nuclear technology Safety Nuclear safety regulation Codes and standards in nuclear safety …
    Published date: 4 April 2025
    NEA Document
    Proceedings of the Working Group on Codes and Standards (WGCS) International Workshop on Mechanical Codes and Standards: In-Service Inspection, 11-14 April 2022
    NEA/CNRA/R(2023)4

    The Nuclear Energy Agency (NEA) Committee on Nuclear Regulatory Activities (CNRA) Working Group on Codes and Standards (WGCS) sponsored a online international workshop on in-service inspection (ISI) ...

    WGCS CNRA Nuclear safety Nuclear technology Inspection Safety Codes and standards in nuclear safety …
    Published date: 4 April 2025
    NEA Document
    SOCRAT (Seismic Simulation of Overhead Crane on Shaking Table) International Benchmark Final Report
    NEA/CSNI/R(2023)11

    Background
    Bridge cranes, which are components that handle devices designed to lift and transfer heavy loads, are widely used in the nuclear sector. Assessing the dynamic behaviour of bridge cranes is...

    Nuclear safety Nuclear safety research CSNI PRG CSNI Safety Benchmark Safety research …
    Published date: 19 March 2025
    NEA Document
    Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications – 2024 Update
    NEA/CSNI/R(2022)10

    The aim of this second revision of the Best Practice Guidelines (BPG) is to provide guidance to the user of computational fluid dynamics (CFD) codes, both novice and experienced, in the field of nucl...

    Nuclear safety Nuclear safety research CSNI PRG CSNI Safety Safety of components and structures Reactor technology Safety research CFD Best practices …
    Published date: 19 March 2025
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