Nuclear reactions relevant to fusion reactor candidate materials

Abstract

There is a possibility to develop the fusion reactors which may offers the prospect newlineof a long-term energy production. For the development of a fusion reactor the reactor newlinematerial should have low radioactivity and high capacity to endure neutron flux. To newlinepredict material damages by nuclear reactions and model the reactor design, accurate and newlinehigh-quality cross-section data are required. newlineThe present study is motivated to investigate the production cross-section of 53Mn newlinedue to neutron induced reactions on stable and unstable target nuclei as well as charge newlineparticle induced reactions on stable target nuclei with the help of a nuclear modular code newlineTALYS-1.9. It is observed that neutron as well as charge particle induced reactions play newlinean important role in the production of 53Mn. newlineMoreover, the production cross-sections of 54Mn, 55Fe, 59Ni and 60Co via charged newlineparticle induced reactions have been calculated by TALYS-1.9. Default input parameters newlineand all the six ldmodels have been used in the calculation of production cross-sections. newlineThe contribution of direct, pre-equilibrium and compound nucleus reaction to the total newlinereaction cross-section are also studied and it is found that the contribution of compound newlinenucleus reaction is high in comparison to direct and pre-equilibrium reaction. newlineEnergy differential cross-section (EDX) and double differential cross-section newline(DDX) of the natural Molybdenum for (n,xp) and (n,xand#945;) reaction at 14.1 MeV neutrons newlineenergy has been calculated by optimizing input parameters of TALYS-1.9. From EDXs newlinecalculation, it is found that most of the outgoing protons and alpha particles have energy newline5 MeV and 13 MeV respectively. DDXs calculated at 10º, 30º,60º, 90º and 120º shows newlineanisotropical distribution of outgoing proton and alpha particles. newlineIn addition to the above, recoil spectra, displacement per atom cross-section and newlinegas production (hydrogen and helium) cross-section for 90Zr, 93Nb, 98Mo, 180Hf, 181Ta newlineand 184W have been calculated to estimate the reactor material damage. NRT method has newlinebeen used to calculate displacement per atom cross-section. Recoil spectra show that newline(n,n ) and (n,2n) reaction channels are major cause to produce recoil nuclei. Gas newlineproduction (hydrogen and helium) cross-section infers that production cross-section of newlinehydrogen is higher than the production cross-section of helium. newlineFrom above, it is concluded that nuclear modular code TALYS-1.9 is a powerful newlinecode to predict the cross-sectional data of long-lived radionuclides induce by neutron as newlinewell as charged particles and damage produced during reactor operation, which is newlineimportant to develop fusion reactor design. newline