Differential and double differential cross sections for neutron induced reactions on Cr, Fe & Ni based on TALYS 1.9
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Date
2018-07
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G.B. Pant University of Agriculture and Technology, Pantnagar - 263145 (Uttarakhand)
Abstract
Sustainable development requires international cooperation and the effective use of technology. The factors contributing to the continuing interest in nuclear power include increasing global demand for energy, as well as concerns about climate change, increasing fossil fuel prices and security of energy supply. There are revolutionary possibilities in the development of fusion reactors. Fusion power offers the prospect of a long-term efficient energy production. Neutron cross-section data are the backbone for the designing of the critical component of fusion reactor. Complete set of neutron cross-section data is one of the urgent requisites for the successful operation of the upcoming fusion reactor. Out of the all the neutron induced reactions, the ones that produce gases are of utmost importance. The generation of hydrogen and helium gases are mainly through (n,p) ( n, n’p), (n,_), (n, n’_) reactions. These reactions are induced on the first wall, structural and blanket components of the reactor. In addition to the production of hydrogen and helium, the other processes such as atomic displacements and transmutations, etc., can produce micro structural defects and damage physical properties of the material. The materials suitable for the reactor structures are stainless steel with Cr, Fe and Ni as the main constituents. Very less experimental data is available for DX and DDX in EXFOR nuclear data library. The main reason can be attributed to the experimental difficulties, such as background counts, detector resolution, particle discrimination, relatively small values of nuclear cross-sections, etc. The present investigation is carried out to find the differential cross-section (DX) and double differential cross-section (DDX) values of Cr, Fe and Ni for (n,xp) and (n,x_) reactions at neutron energy 14.1 and 14.6MeV using TALYS-1.9. The contributions from direct, pre-equilibrium and compound nucleus processes to the total reaction are studied along with the study of all the open reaction channels for (n,xp) and (n,x_) reaction.
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