Abstract
The slowing down spectrum and reaction-rate ratios of the Cf-252 spontaneous source in moderating media of the University of Tehran Irradiation Facility (UTIF) are calculated using the ANISN one-dimensional transport code. In these calculations the UKNDL 37 group structure cross section is used with isotropic scattering (PO). The effect of the number of mesh intervals, degrees of approximation (SN), irradiation facility geometry (spherical or cylindrical) and moderating materials on the shape of the neutron spectrum are studied in detail. The reaction cross sections set are derived from the ENDF-B/IV Nuclear Data Library. Twelve reactions are calculated and their ratios are found to the most fundamental reaction, U-235 (n, f).
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References
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© 1985 Springer Science+Business Media Dordrecht
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Azimi-Garakani, D., Rahbar, M., Fouladi-Oskoui, N. (1985). Calculation of the 252cF Neutron Slowing Down Spectrum and Reaction Rate Ratios in Moderating Media. In: Genthon, J.P., Röttger, H. (eds) Reactor Dosimetry. Springer, Dordrecht. https://doi.org/10.1007/978-94-010-9726-0_5
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DOI: https://doi.org/10.1007/978-94-010-9726-0_5
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