Determination of 55Mn(n,γ)56Mn reaction cross-section at the neutron energies of 1.12, 2.12, 3.12 and 4.12 MeV
Author:
Vansola Vibha1, Mukherjee Surjit1, Naik Haladhara2, Suryanarayana Saraswatula Venkata3, Ghosh Reetuparna4, Badwar Sylvia4, Lawriniang Bioletty Mary4, Sheela Yerraguntla Santhi5
Affiliation:
1. Department of Physics, Faculty of Science, M. S. University of Baroda, Vadodara-390002, India 2. Radiochemistry Division, Bhabha Atomic Research Center, Trombay, Mumbai-400085, India 3. Nuclear Physics Division, Bhabha Atomic Research Centre, Mumbai-400085, India 4. Department of Physics, North Eastern Hill University, Shillong, Meghalaya-793022, India 5. Department of Statistics, Manipal University, Manipal-576104, India
Abstract
Abstract
The 55Mn(n,γ)56Mn reaction cross-sections at the neutron energies of 1.12, 2.12, 3.12 and 4.12 MeV were determined by using activation and off-line γ-ray spectrometric technique. The neutron energies of 1.12 and 2.12 MeV were generated from the 7Li(p,n) reaction by using the proton energies of 3 and 4 MeV from the folded tandem ion beam accelerator (FOTIA) at BARC. For the neutron energies of 3.12 and 4.12 MeV, the proton energies used were 5 and 6 MeV from the Pelletron facility at TIFR, Mumbai. The 115In(n,γ)116mIn reaction cross-section was used as the neutron flux monitor. The 55Mn(n,γ)56Mn reaction cross-section at the neutron energies of 4.12 MeV are reported for the first time, whereas at 1.12, 2.12 and 3.12 MeV, they are in between the literature data. The 55Mn(n,γ)56Mn reaction cross-section was also calculated theoretically by using the computer code TALYS 1.6 and EMPIRE 3.2.2. The experimental data of present work are found to be in between the theoretical values of TALYS and EMPIRE.
Publisher
Walter de Gruyter GmbH
Subject
Physical and Theoretical Chemistry
Reference46 articles.
1. Sinha, R. K., Kakodkar, A.: Design and development of the AHWR – the Indian thorium fuelled innovative nuclear reactor. Nucl. Eng. Des. 236, 683 (2006). 2. Allen, T. R., Crawford, D. C.: Lead-cooled fast reactor systems and the fuels and materials challenges. Sci. Technol. Nucl. Install., 2007, 11 (2007). 3. Nuttin, A., Heuer, D., Billebaud, A., Brissot, R., Le Brun, C., Liatard, E., Loiseaux, J. M., Mathieu, L., Meplan, O., Merle-Lucotte, E., Nifenecker, H., Perdu, F., David, S.: Potential of thorium molten salt reactors detailed calculations and concept evolution with a view to large scale energy production. Prog. Nucl. Energy 46, 77 (2005). 4. Mathieu, L., Heuer, D., Brissot, R., Garzenne, C., Lebrun, C., Liatard, E., Loiseaux, J. M., Meplan, O., Merle-Lucotte, E., Nuttin, A.: Proportion for a very simple thorium molten salt reactor, in Proceedings of the Global International Conference, Paper No. 428, Tsukuba, Japan, 2005. 5. Fast reactors and accelerator driven systems knowledge base, IAEA- TECDOC-1319: thorium fuel utilization: options and trends (Nov. 2002).
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