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    Event
    Analytical Benchmarks: Case Studies in Neutron Transport Theory (ABNTT)
    24 - 28 November 2025
    Paris, France
    Date: 24-28 November 2025
    Place: NEA Headquarters
                46, Quai Alphonse Le Gallo
                92100 Boulogne-Billancourt (Paris) - FRANCE
    Minimum enrollment: 12 participants
    Maximum enrollment: 20 participan...
    Transport CPS Data Bank Benchmark
    Published date: 18 February 2025
    Event
    FUDGE/(MC)GIDI/GNDS introductory course
    10 - 13 June 2025
    Online training course
    Date: 10-13 June 2025 16:00-21:00 CEST-Paris 
    Place: Online training course
    Minimum enrollment: 6 participants
    Maximum enrollment: 22 participants
    Course fee: 50 EUR
    Registration deadline: 28 M...
    CPS Codes and programs Reactor physics Data Bank Training Nuclear data processing ENDF …
    Published date: 5 May 2025
    Event
    Advanced MCNP6®
    19 - 23 May 2025
    Paris, France

    Photo credit: Joel A. Kulesza, Roger Lee Martz, LANL LA-UR-17-23854

    ----------------------------------The course is full -----------------------------------

    Date: 19-23 May 2025
    Place: NEA Headq...
    Physics Modelling and simulation Monte Carlo method Transport CPS Data Bank Training …
    Published date: 5 February 2025
    Event
    Intermediate MCNP6®
    12 - 16 May 2025
    Paris, France

    Photo credit: Joel A. Kulesza, Roger Lee Martz, LANL LA-UR-17-23854

    ----------------------------------The course is full -----------------------------------
    Date: 12-16 May 2025
    Place: NEA Headq...
    Physics Modelling and simulation Monte Carlo method Transport CPS Data Bank Training …
    Published date: 5 February 2025
    Activity
    SINBAD - Shielding Integral Benchmark Archive and Database

    https://www.oecd-nea.org/tools/ierequest/start/package/NEA-1939%2501The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for more than 100 reactor shielding, ...

    Transport Experiments Radiation Databases Radiation transport and shielding Reactor physics Integral experiments Verification and validation Validation SINBAD Benchmark …
    Published date: 14 April 2025
    Event
    SERPENT-2 online training course for beginners
    7 - 11 April 2025
    Online training course

    Dates: 7-11 April 2025
    Time: 17:00-21:00 (CEST, Paris time)/10:00-14:00 (CDT USA/Mexico)/12:00-16:00 (UTC-3, Argentina)
    Minimum enrollment: 12 participants
    Maximum enrollment: 15 participants
    Registratio...

    Modelling and simulation Reactor physics Monte Carlo method Radiation shielding Data Bank Training …
    Published date: 5 February 2025
    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: 4 April 2025
    Event
    NJOY Training Course
    2 - 6 December 2024
    NEA, Paris, France
    Date: 2-6 December 2024
    Place: OECD/NEA Headquarters
                46, Quai Alphonse Le Gallo
                92100 Boulogne-Billancourt (Paris) - FRANCE
    Minimum enrollment: 15 participants
    Maximum enrollment: 20 parti...
    CPS Codes and programs Reactor physics Data Bank Training Nuclear data processing ENDF …
    Published date: 26 June 2024
    Event
    SERPENT-2 in-person training course for beginners
    19 - 22 November 2024
    Paris, France

    Dates: 19-22 November 2024
    Minimum enrollment: 12 participants
    Maximum enrollment: 20 participants
    Registration fee: 750 EUR
    Registration deadline: 27 September 2024
    Contact: hedvig.nahon@oecd-nea.org wit...

    Modelling and simulation Reactor physics Monte Carlo method Radiation shielding Data Bank Training …
    Published date: 31 October 2024
    Activity
    SFCOMPO 2.0 (Spent Fuel Isotopic Composition)

    SFCOMPO 2.0 (Spent Fuel Isotopic Composition) is a relational database designed to facilitate the search and visualisation of experimental assay data of spent nuclear fuel.

    Criticality safety Verification and validation Databases
    Published date: 1 October 2024
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