Programa científico

I. Nuclear data for nuclear technologies and applications
Seminars on:
What are nuclear data?
Nuclear data for nuclear technologies and applications
The JEFF project

II. Identification of nuclear data priorities
Seminars on:
Nuclear data for reactor physics (thermal and fast systems)
Nuclear data and sensitivity analyses
Nuclear data and fuel cycle
Nuclear data priorities for non-energy applications

Lectures with computer on:
Introduction to sensitivity analyses
Methodologies used in sensitivity analyses
Sensitivity analyses of thermal reactors
Sensitivity analyses of fast reactors

III. Nuclear data measurements
Seminars on:
Facilities and experimental techniques: reactions (neutron beams, reactors)
Facilities and experimental techniques: decay data (accelerators)
Samples for nuclear data experiments
Detectors and experimental techniques
Identification and propagation of uncertainties
Dissemination of nuclear data

Lectures with computer on:
Capture experiments
Fission experiments
Transmission experiments
Data reduction
Data analysis

IV. Evaluation
Seminars on:
Nuclear data evaluation
Automatic evaluation procedures

V. Verification and validation
Seminars on:
Data processing tools, simulation codes (Monte Carlo and deterministic) and reference databases of integral experiments
Validation of nuclear data libraries

Lectures with computer on:
Nuclear data visualisation tools
Nuclear data processing tools
Searching the databases
Validation with integral experiments

  • Nuclear data for nuclear technologies

    Applications/examples of calculations related to:

    • Nuclear safety
    • Reactor design
    • Nuclear fuel cycle
    • Non energy applications
    • Compilation of nuclear data in international databases for different applications.
    • International agencies.
  • Identification of nuclear data priorities

    1. Prior knowledge in the actual nuclear data libraries.
    2. Physical quantities and uncertainties.
    3. New nuclear data needs and priorities.
    4. Sensitivity analysis.
  • Nuclear data measurements

    1. Quantities to be measured

    1. Nuclear reactions: cross sections, secondary product yields
    2. Decay data
    3. Possible sources of uncertainty: type I (statistical) and type II (systematic).

    2. Experimental techniques and detectors

    • Particle induced reaction measurements: neutrons (total, fission, capture and inelastics), charged particles and 𝝲-rays.
    • Decay data. Measure the complete decay properties: T1/2, particle spectra and correlations.

    3. Preparation of adequate samples

    Raw material, sample preparation techniques.

    4. Different facilities for nuclear data measurements:

    -Neutron sources, (radioactive) ion beam facilities, metrology laboratories.

    6. Data analysis and uncertainty assessment

    • Standard / custom analysis codes.
    • Identification and estimation of uncertainties.

    7. Dissemination

    • Data + uncertainties (covariance matrix).
    • The EXFOR database.
  • Evaluation of nuclear data

    • Modelling of the disseminated data.
    • Preparation of ENDF files (or new formats) and first validation.
    • Compilation and release of the general/specific libraries.
  • Verification and validation

    Integral experiments and reference databases: ICSBEP, SFCOMPO, IRPhE, ENSDF, SINBAD…
    Processing of the files for the different simulation codes: multigroup, pointwise, different temperatures...
    Deterministic and Monte Carlo simulation codes: MCNP, ERANOS, TRIPOLI, SERPENT, SCALE, OPENMC, GEANT4…
    Comparison of calculations with integral experiments.
    International benchmarks.