SUMMARY
This discussion focuses on finding neutron capture and fission cross sections, particularly for Thorium-232 and Uranium-233, utilizing resources like the ENDF VII and NNDC databases. Users shared links to the NNDC site for retrieving cross-section data, highlighting discrepancies between calculated values and those found in IAEA's TECDOC 1450. The conversation emphasizes the importance of understanding integrated values over thermal spectra and the need for clarity in interpreting data from nuclear databases.
PREREQUISITES
- Understanding of neutron capture and fission cross sections
- Familiarity with ENDF VII and NNDC databases
- Knowledge of thermal neutron spectra and energy ranges
- Basic nuclear physics concepts, particularly related to Uranium and Thorium isotopes
NEXT STEPS
- Research the latest updates on ENDF VII for neutron cross-section data
- Learn how to effectively navigate and interpret the NNDC database
- Study the differences between integrated values and single energy cross sections
- Explore additional resources such as IAEA's TECDOC 1450 for comparative analysis
USEFUL FOR
Nuclear physicists, researchers in reactor design, and students studying nuclear engineering who require accurate data on neutron interactions with Thorium and Uranium isotopes.