Track 1. Codes and other calculation methods
- New features, methods
- Codes validation
- Algorithms, deep learning, etc.
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Track 2. Nuclear Data
- Evaluation of nuclear data, including covariances
- Processing tools
- Validation of nuclear data
- Experimental needs
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Track 3. Uncertainty and Sensitivity Analysis
- Derivation of code/data bias and its uncertainty
- Generation and use of covariance data
- U/S analysis methods and applications to UNF
- Uncertainty propagation
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Track 4. Measurements, Experiments and Benchmarks
- Improvements in measurement technics used for codes validation (experiments, reactor operation, accidents, etc.).
- New experiments, new benchmarks
- Future experimental programme
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Track 5. Standards, Assessment Methodology, Regulations
- National and international guides, standards, handbooks
- New safety assessment methodologies
- National/international regulations
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Track 6. Operational Practices and Safety cases
- Specific safety cases
- Lessons learnt from events
- Good practices
- Fuel cycle facilities (front-end and back-end)
- Current experimental needs
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Track 7. Storage and Transport issues
- Applications involving fresh or used fuel, or waste containing fissile material in storage and transport
- Burn-up credit applications
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Track 8. Final disposal issues
- Issues related to fissile material/ waste in final disposal
- Burn-up credit applications
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Track 9. Criticality Accidents and Incidents
- Emergency preparedness and response
- CAAS
- Lessons learnt from near misses and accidents
- Criticality accident modelling
- Criticality accident dosimetry
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Track 10. Professional Development Issues and Training
- Maintaining competencies
- Education, training programmes for practitioners, regulators, experimenters, etc.
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Track 11. Future Challenges
- New reactors and fuel types, etc.
- New processes
- Identification and solution to past and current difficulties.
- Future experimental needs
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