Khorasanov G.L., Blokhin А.I.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
In the paper the values of one-group neutron radiation capture cross sections,
<σ(n,γ)>, for coolant consisted from lead-208 averaged over neutron spectra of FRs and
ADSs are calculated. It is shown that they are by 4-7 times smaller than one–group cross sections
for coolant consisted from lead natural and lead-bismuth. This permits to consider the
coolant from lead-208 as a low neutron absorption coolant for FRs and ADSs. The small value
of cross section for lead-208 and surplus of neutrons in the reactor core and its periphery can
be used for reducing the fuel load, increasing the breeding gain and transmutation of long living
fission products into short living nuclides.
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