title: Activation analysis and first occupational dose rates estimates for the Laser Megajoule facility.
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.
authors.affiliation: CEA, BP12 Bruyères-le-Châtel, 91680 France. henri.jacquet@cea.fr
authors.forename: H P
authors.initials: HP
authors.lastname: Jacquet
authors.forename: L
authors.initials: L
authors.lastname: Lachèvre
authors.forename: M
authors.initials: M
authors.lastname: Messaoudi
mesh_terms: D001822:Body Burden; D003198:Computer Simulation; D005602:France; D005720:Gamma Rays; D007834:Lasers; D008954:Models, Biological; D015233:Models, Statistical; D009010:Monte Carlo Method; D009502:Neutrons; D016273:Occupational Exposure / Q000032:analysis*; D011829:Radiation Dosage; D011834:Radiation Monitoring / Q000379:methods*; D011835:Radiation Protection / Q000295:instrumentation* / Q000379:methods; D012062:Relative Biological Effectiveness