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Peer-reviewedCC BY 4.0Annals of Nuclear Energy

NUCLEA: A thermodynamic database validated for severe accident codes ☆

Abstract

The objective of this article is to present an overview of the validation of the NUCLEA thermodynamic database through a comparative analysis with experimental data. These examples are selected from important experimental programs (notably OECD MASCA, EC ENTHALPY) in order to cover various important topics for improving severe accident codes, especially regarding the progression of corium inside or outside the vessel. The comparison between calculations and measurements is discussed, and the main lessons learned from this extensive validation work are summarized, along with an assessment of the current relevance of the NUCLEA database concerning the thermodynamics of corium. Based on these results, the validity domain of NUCLEA is defined, and prospects for future improvement are proposed.

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BibTeX
@article{barrachin2026nuclea,
  title = {{NUCLEA: A thermodynamic database validated for severe accident codes ☆}},
  author = {Marc Barrachin and Bénédicte Michel and Bruno Piar and E Fischer},
  journal = {Annals of Nuclear Energy},
  year = {2026},
  month = sep,
  doi = {10.1016/j.anucene.2026.112851},
  url = {https://asnr.hal.science/hal-05762140v1},
  note = {CC BY 4.0},
}
RIS
TY  - JOUR
TI  - NUCLEA: A thermodynamic database validated for severe accident codes ☆
AU  - Marc Barrachin
AU  - Bénédicte Michel
AU  - Bruno Piar
AU  - E Fischer
PY  - 2026
DA  - 2026/09/24
JO  - Annals of Nuclear Energy
DO  - 10.1016/j.anucene.2026.112851
UR  - https://asnr.hal.science/hal-05762140v1
AB  - The objective of this article is to present an overview of the validation of the NUCLEA thermodynamic database through a comparative analysis with experimental data. These examples are selected from important experimental programs (notably OECD MASCA, EC ENTHALPY) in order to cover various important topics for improving severe accident codes, especially regarding the progression of corium inside or outside the vessel. The comparison between calculations and measurements is discussed, and the main lessons learned from this extensive validation work are summarized, along with an assessment of the current relevance of the NUCLEA database concerning the thermodynamics of corium. Based on these results, the validity domain of NUCLEA is defined, and prospects for future improvement are proposed.
SN  - 0306-4549
ER  -