Activation of Mn, Li2O and LiF in the JSI TRIGA reactor to study potential tritium production monitors for fusion applications

Two series of measurements were performed in the JSI TRIGA research reactor in 2014 and 2017 to validate the 55 Mn(n, γ ) 56 Mn cross-sections and experimentally investigate the relationship between the 55 Mn(n, γ ) 56 Mn reaction and the rate of tritium production through the 6 Li(n,t) 4 He reaction. Indeed, previously observed similarities between the sensitivity profiles of the neutron reaction of tritium production on lithium, 6 Li(n,t) 4 He, and those of the 55 Mn(n, γ ) 56 Mn reaction in tritium breeder modules indicated that the latter reaction could be used as an effective monitor of tritium production, at least for short-term monitoring (the half-life of 56 Mn being 2.579 h). However, experimental verification, improvements and validation of the 55 Mn(n, γ ) 56 Mn cross-sections are needed in order to meet the required accuracy. Foils of certified reference material Al–1%Mn, as well as LiF thermoluminescent detectors and Li 2 O samples were irradiated, both bare and under cadmium, to study the potential use of the 55 Mn(n, γ ) 56 Mn reaction for monitoring tritium production in fusion devices. Additionally, Al–0.1%Au was also irradiated for comparison, the 197 Au(n, γ ) 198 Au reaction cross-section being a standard. In order to obtain complementary information for data validation purposes, the irradiations were performed in positions within the JSI TRIGA reactor with different neutron spectra, i.e. in the central channel, the pneumatic tube and the F19 position, both in the outer ‘F’ ring of the reactor core and in the IC-40 irradiation channel located in the graphite reflector surrounding the reactor core. Bare and cadmium-covered irradiations were needed to subtract the contribution of epithermal neutrons to the 55 Mn(n, γ ) 56 Mn reaction. Calculations of the reaction rates were performed using the Monte Carlo code MCNP6.1 with a detailed model of the JSI TRIGA reactor, with the samples, the irradiation capsules and covers being modelled explicitly. The uncertainties involved in the measurements and the calculations were carefully evaluated. The principal objective was to study the energy response and correlations between the 55 Mn(n, γ ) 56 Mn reaction in irradiated Al–1%Mn and the 6 Li(n,t) 4 He reaction in irradiated LiF and Li 2 O. Good consistency between the measured and calculated 55 Mn(n, γ ) 56 Mn and 197 Au(n, γ ) 198 Au reaction rates, in most cases within the uncertainty bars, was observed.