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Experimental Validation of Neutron Spectra Calculated via Transport Codes

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Reactor Dosimetry

Abstract

The results of discrete ordinate DOT calculations are compared with Multiple Foil Activation measurements performed at RB-2/TV research facility (Montecuccolino Laboratories, Bologna) and at Caorso power plant (Caorso, Piacenza).

Comparisons indicate that integral neutron fluxes can be predicted within about 10%, whereas experimental flux shapes in some cases may deviate significantly from the computed ones, especially at neutron energies higher than 2 MeV.

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References

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© 1985 Springer Science+Business Media Dordrecht

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Borioli, E., Sandrelli, G., Cesana, A., Sangiust, V., Terrani, M. (1985). Experimental Validation of Neutron Spectra Calculated via Transport Codes. In: Genthon, J.P., Röttger, H. (eds) Reactor Dosimetry. Springer, Dordrecht. https://doi.org/10.1007/978-94-010-9726-0_6

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  • DOI: https://doi.org/10.1007/978-94-010-9726-0_6

  • Publisher Name: Springer, Dordrecht

  • Print ISBN: 978-94-010-9728-4

  • Online ISBN: 978-94-010-9726-0

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