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Nuclear fusion is one of the world’s primary energy sources. Studies on the structural fusion materials are very important in terms of the development of fusion technology. Chromium, nickel, zinc, scandium, titanium,and yttrium are important structural fusion materials. In this paper, for use in nuclear science and technology applications, the excitation functions of the ~(50)Cr(d, n)~(51)Mn,~(58)Ni(d, n)~(59)Cu,~(64)Zn(d, n)~(65)Ga,~(66)Zn(d, n)~(67)Ga,~(45)Sc(d,2n)~(45)Ti,~(47)Ti(d, 2n)~(47)V,~(48)Ti(d, 2n)~(48)V, and ~(89)Y(d, 2n)~(89)Zr nuclear reactions were investigated. The calculations that are based on the pre-equilibrium and equilibrium reaction processes were performed using ALICE–ASH computer code. A comparison with geometry-dependent hybrid model has been made using the initial exciton numbers n_0= 4–6 and level density parameters α = A/5; A/8; A/11.Also, the present model-based calculations were compared with the cross sections obtained using the formulae suggested from our previous studies. Furthermore, the cross section results have been compared with TENDL data based on TALYS computer code and the measured data in the literature.
Nuclear fusion is one of the world’s primary energy sources. Studies on the structural fusion materials are very important in terms of the development of fusion technology. Chromium, nickel, zinc, scandium, titanium, and yttrium are important structural fusion materials. In this paper , for use in nuclear science and technology applications, the excitation functions of ~ (50) Cr (d, n) ~ (51) Mn, ~ Zn, Ni, Ga, ~ (45) Sc (d, 2n) ~ (45) Ti, ~ (47) Ti (48) Ti (d, 2n) ~ (48) V and ~ (89) Y (d, 2n) ~ (89) Zr nuclear reactions were investigated. that are based on the pre-equilibrium and equilibrium reaction processes were performed using ALICE-ASH computer code. A comparison with geometry-dependent hybrid model has been made using the initial exciton numbers n_0 = 4-6 and level density parameters α = A / 5; A / 8; A / 11. Also, the present model-based calculations were compared with the cross sections obtained using the formula suggested (f rom our previous studies. furthermore, the cross section results have been compared with TENDL data based on TALYS computer code and the measured data in the literature.