Speaker
Description
The light particle induced reaction cross-section data are of prime interest for the different areas like radiation dose estimation, radiation damage, fuel cycle assessments, transmutation of long lived nuclei and many more. The future nuclear reactors like Accelerator Driven Subcritical systems (ADSs), International Experimental Thermonuclear Reactor (ITER) and fast breeder reactors demand the neutron and proton induced reaction cross-sections data at high incident energies. The data will also be helpful for the advancement of medical accelerators and for the medical isotope production. We have made an attempt to understand the nature of the cross-section data for reactor fuel materials (238U, 232Th) [1, 2] and structural materials (Sn, Tb, W, Gd, Ni, Al, In) [3,4,5] within the neutron energies from threshold to 22 MeV. The proton induced reaction cross-sections were also measured for the reactor structural materials (Ag, Ti, Nb, and Sn) [6, 7] within 10-22 MeV energies. In addition to this, we have also measured the cross-sections for the most demanding medical isotope 99mTc using two production routes 100Mo(n, 2n)99mMo [8] and 100Mo(p, 2n)99mTc.The experiments were carried out at the 14UD BARC-TIFR Pelletron accelerator utilizing the activation and off-line γ-ray measurement technique for both neutron and proton irradiations. The quasi-monoenergetic neutrons of desired energies were generated using the 7Li(p, n) (Eth = 1.88 MeV) reaction. The nuclear model codes like, TALYS-1.9 [9], ALICE-2014 [10] and EMPIRE-3.2.3 [11] were used for the theoretical predictions. The uncertainty in each measured data was calculated using the error propagation method [1]. The uncertainties together with the correlation coefficients were calculated for each case and were found to be within the range of 10-20%. The recent work emphasis the vitality of the reaction cross-section data for the reactor based applications. The work also highlights that the precise reaction cross-section data is achievable within 20% uncertainty by using the 7Li(p, n) reaction as the neutron generator.
REFERENCES
[1]. Siddharth Parashari et al., Phys. Rev. C 98 (2018) 014625.
[2]. S. Mukherjee et al., App. Rad. Isot. 143 (2019) 72–78.
[3]. Siddharth Parashari et al., Appl. Rad. Iso. 133 (2018) 31–37.
[4]. R. Makwana et al., Phys. Rev. C 96 (2017) 024608.
[5]. B.K. Soni et al., Appl. Rad. Iso. 141 (2018) 10-14.
[6]. Siddharth et al., Nucl. Phys. A 978 (2018) 160-172.
[7]. Siddharth et al., Nucl. Phys. A 979 (2018) 102-112.
[8]. Siddharth Parashari et al., 2018 19th International Scientific Conference on Electric Power Engineering (EPE). ) https://doi.org/10.1109/EPE.2018.8395960.
[9]. A. J. Koning et al., TALYS user manual a nuclear reaction program, User manual. NRG-1755 ZG PETTEN, The Netherlands (2015).
[10]. M. Blann, Phys. Rev. C 54 (1996)1341.
[11]. M. Herman, et al., EMPIRE-3.2 Malta modular system for nuclear reaction calculations and nuclear data evaluation, INDC(NDS)-0603, BNL-101378-2013.
