Abstract
A neutron multiplication coefficient, ${k}_{\mathrm{eff}}$, has been estimated for spallation neutron flux using the data of spectrum average cross sections of all absorption, fission, and nonelastic reaction channels of $^{232}\mathrm{Th}$, $^{238}\mathrm{U}$, $^{235}\mathrm{U}$, and $^{233}\mathrm{U}$ fuel elements. It has been revealed that in spallation neutron flux (i) nonfission, nonabsorption reactions play an important role in the calculation of ${k}_{\mathrm{eff}}$, (ii) one can obtain a high value of ${k}_{\mathrm{eff}}$ even for fertile $^{232}\mathrm{Th}$ fuel, which is hardly possible in a conventional fast reactor, and (iii) spectrum average absorption cross sections of neutron poisons of a conventional reactor are relatively very small.
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