Reaction rates and neutron spectra in the FFTF at full power
D.W. Wootan, J.A. Rawlins, K.D. Dobbin
Abstract
D.W. Wootan, J.A. Rawlins, K.D. Dobbin
Abstract
Results from the HP irradiation test have been shown to reduce uncertainties associated with calculation of axial and radial flux and reaction rate distributions, flux perturbations due to core heterogeneities, neutron flux and reaction rates outside the fuel region, activation of structural components and sodium, and fuel burnup. Improved knowledge of reaction rates (hence burnup, power and flux distributions) is expected to result in better prediction of the performance of experiments irradiated in FFTF.
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Results from the HP irradiation test have been shown to reduce uncertainties associated with calculation of axial and radial flux and reaction rate distributions, flux perturbations due to core heterogeneities, neutron flux and reaction rates outside the fuel region, activation of structural components and sodium, and fuel burnup. Improved knowledge of reaction rates (hence burnup, power and flux distributions) is expected to result in better prediction of the performance of experiments irradiated in FFTF.
Key concepts: Burnup, Neutron flux, Flux (metallurgy), Nuclear engineering, Neutron, Materials science, Neutron transport, Reaction rate