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1.	Griffin, Peter J., et al. (author) Nuclear Reaction Data and Uncertainties for Radiation Damage : Summary Report of the Technical Meeting, IAEA Headquarters, Vienna, Austria13 – 16 June 2016 2016 Reports (other academic/artistic)abstract This Meeting was organized to implement the recommendation of the second Research Coordinated Meeting (RCM) of the International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP) “Primary Radiation Damage Cross Sections” to analyse the accuracy and consistency of the radiation damage-relevant nuclear data in the major nuclear data evaluations with the eventual goal of identifying the most reliable data and provide quantitative uncertainty estimates. Participants have considered the status of the primary nuclear data, such as recoils spectra in the latest releases of ENDF, JEFF, JENDL, FENDL, ROSFOND and TENDL, the ways of deriving the damage quantities KERMA, NRT- or arc-dpa and gas production cross sections as well as the recipes for an assessment of their uncertainties. This report contains the contemporary view of the Meeting participants on these issues in the form of a consolidated set of statements, recommendations and individual summaries.

Griffin, Peter J., et al. (author)
Nuclear Reaction Data and Uncertainties for Radiation Damage : Summary Report of the Technical Meeting, IAEA Headquarters, Vienna, Austria13 – 16 June 2016
2016
Reports (other academic/artistic)abstract
- This Meeting was organized to implement the recommendation of the second Research Coordinated Meeting (RCM) of the International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP) “Primary Radiation Damage Cross Sections” to analyse the accuracy and consistency of the radiation damage-relevant nuclear data in the major nuclear data evaluations with the eventual goal of identifying the most reliable data and provide quantitative uncertainty estimates. Participants have considered the status of the primary nuclear data, such as recoils spectra in the latest releases of ENDF, JEFF, JENDL, FENDL, ROSFOND and TENDL, the ways of deriving the damage quantities KERMA, NRT- or arc-dpa and gas production cross sections as well as the recipes for an assessment of their uncertainties. This report contains the contemporary view of the Meeting participants on these issues in the form of a consolidated set of statements, recommendations and individual summaries.

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