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Updated: Aug 9, 2026

Laser-heating and Radiance Spectrometry for the Study of Nuclear Materials in Conditions Simulating a Nuclear Power Plant Accident
Published on: December 14, 2017
Activation analysis and first occupational dose rates estimates for the Laser Megajoule facility
H P Jacquet1, L Lachèvre, M Messaoudi
1CEA, BP12 Bruyères-le-Châtel, 91680 France. henri.jacquet@cea.fr
Abstract:
A three-dimensional neutronic modelling of the LMJ facility has been performed. The Monte Carlo transport code TRIPOLI is used to obtain the neutron spectra required for the inventory code FISPACT. Nodal activation responses and time-dependent decay gamma spectra are produced and used as source terms for further treatment by TRIPOLI for a range of engineering and safety assessments. It is shown that three-dimensional neutronic and nodal activation can be performed in a convenient way and the results obtained by this procedure will serve as a data-base for design and S&E analysis.
