Measurement of 64Zn(n,2n)63Zn and 67Zn(n,p)67Cu reaction cross sections at neutron energies of 17.10 ± 0.82 and 14.98 ± 0.81 MeV.
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| Title: | Measurement of 64Zn(n,2n)63Zn and 67Zn(n,p)67Cu reaction cross sections at neutron energies of 17.10 ± 0.82 and 14.98 ± 0.81 MeV. |
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| Authors: | Chauhan, Rakesh1 (AUTHOR) rakeshphysics@gmail.com, Singh, R. K.1 (AUTHOR), Singh, N. L.1,2 (AUTHOR) nl.singh-phy@msubaroda.ac.in, Mehta, Mayur3 (AUTHOR), Makwana, Rajnikant1 (AUTHOR), Suryanarayana, S. V.4 (AUTHOR), Mukherjee, S.1 (AUTHOR), Nayak, B. K.5 (AUTHOR), Katovsky, K.6 (AUTHOR) |
| Source: | Journal of Radioanalytical & Nuclear Chemistry. Sep2025, Vol. 334 Issue 9, p6521-6528. 8p. |
| Subjects: | Zinc, Absorption cross sections, Mathematics, Nuclear activation analysis, Gamma ray spectroscopy, Neutron temperature |
| Abstract: | Cross sections for the 64Zn(n,2n)63Zn and 67Zn(n,p)67Cu reactions were measured at neutron energies of 17.10 ± 0.82 and 14.98 ± 0.81 MeV by neutron activation techniques and offline γ-ray spectroscopy method. Production of neutron was done by 7Li (p , n) reaction. The 27Al (n , α) 24Na reaction was used as a neutron flux monitor. Estimations were performed using TALYS-1.95 and EMPIRE 3.2.2 codes with default values. The measured cross sections were compared with literature data taken from the EXFOR database and the latest evaluated data from the ENDF/B-VIII.0, JEFF-3.3, JENDL-5.0 and TENDL-2021 libraries. [ABSTRACT FROM AUTHOR] |
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| Database: | Engineering Source |
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| Abstract: | Cross sections for the 64Zn(n,2n)63Zn and 67Zn(n,p)67Cu reactions were measured at neutron energies of 17.10 ± 0.82 and 14.98 ± 0.81 MeV by neutron activation techniques and offline γ-ray spectroscopy method. Production of neutron was done by 7Li (p , n) reaction. The 27Al (n , α) 24Na reaction was used as a neutron flux monitor. Estimations were performed using TALYS-1.95 and EMPIRE 3.2.2 codes with default values. The measured cross sections were compared with literature data taken from the EXFOR database and the latest evaluated data from the ENDF/B-VIII.0, JEFF-3.3, JENDL-5.0 and TENDL-2021 libraries. [ABSTRACT FROM AUTHOR] |
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| ISSN: | 02365731 |
| DOI: | 10.1007/s10967-024-09789-9 |
