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Report No.

Evaluation of neutron capture cross section on $$^{205}$$Pb with photonuclear data

Iwamoto, Nobuyuki ; Shizuma, Toshiyuki*

Transmutation and reduction of high level radioactive wastes (e.g. minor actinides) produced in nuclear reactors are expected by an accelerator driven system (ADS). Japan Atomic Energy Agency proposed that Pb and Bi are used as a spallation target and coolant. The neutronics design was performed without including $$^{205}$$Pb, which is a long-lived radioactive nuclide with half-life of 1.7$$times$$10$$^{7}$$ years and thus has long-lasting radiotoxicity. $$^{205}$$Pb is produced by the neutron capture reaction on $$^{204}$$Pb. In order to evaluate the accumulated amount of $$^{205}$$Pb, the neutron capture cross section of $$^{205}$$Pb is needed. However, it has not been measured in the keV to MeV neutron energy region. In the present work the calculations of cross sections were performed by the nuclear reaction calculation code, CCONE. Measured photonuclear data of ($$gamma$$,$$gamma$$) reaction and photoneutron cross sections were used to evaluate photon strength function of $$^{206}$$Pb. The ($$gamma$$,$$gamma$$) reaction data used were newly obtained by an experiment at HZDR. The fixed photon strength function was applied to calculate the neutron capture cross sections of $$^{205}$$Pb. The resulting cross section is smaller than the data of $$^{204}$$Pb in the relevant energy region.



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