Verification of neutron fission cross-sections of minor actinides from some
recently available evaluated nuclear data libraries was carried out by
comparison of the reaction rates calculated by the MCNP6.1 computer code to
the experimental values. The experimental samples, containing thin layers of
235U, 237Np, 238,239,240,241Pu, 242mAm, 243Cm, 245Cm, and 247Cm, deposited on
metal support and foils of 235U (pseudo-alloy 27Al + 235U), 238U, natIn,
64Zn, 27Al, and multi-component sample alloy 27Al + 55Mn + natCu + natLu +
197Au, were irradiated in the channels of the tank containing fluorine salts
0.52NaF + 0.48ZrF4, labelled as the Micromodel Salt Blanket, inserted in the
lattice centre of the MAKET heavy water critical assembly at the Institute
for Theoretical and Experimental Physics, Moscow. This paper is a
continuation of earlier initiated scientific-research activities carried out
for validation of the evaluated fission cross-sections of actinides that were
supposed to be used for the quality examination of the fuel design of the
accelerator driven systems or fast reactors, and consequently, determination
of transmutation rates of actinides, and therefore, determination of
operation parameters of these reactor facilities. These scientific-research
activities were carried out within a frame of scientific projects supported
by the International Science and Technology Center and the International
Atomic Energy Agency co-ordinated research activities, from 1999 to 2010.
Obtained results confirm that further research is needed in evaluations in
order to establish better neutron cross-section data for the minor actinides
and selected nuclides which could be used in the accelerator driven systems
or fast reactors.
Benefits in Using Lead-208 Coolant for Fast Reactors and Accelerator Driven Systems
