Model Calculations of Neutron Excitation functions
Neutron activation cross-section on the structural materials of miniature neutron source reactor. NIRR1
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A miniature neuron source reactor NNIR-1 contained some impurities on the beryllium shim serving as a neuron reflector, a research was conducted using EXIFON CODE, a computational code to calculate the excitation function ( activation cross section)in the range of (0-10Mev) as a result of neutron induced reaction (n, alpha) (n,p)., Results were compared with Experimental result from EXFOR DATA library and were in good agreement, the simulation was done in order to ascertain the integrity of the structural material of the reactor and the problem of hydrogen and heluim gas formation on beryllium...
A miniature neuron source reactor NNIR-1 contained some impurities on the beryllium shim serving as a neuron reflector, a research was conducted using EXIFON CODE, a computational code to calculate the excitation function ( activation cross section)in the range of (0-10Mev) as a result of neutron induced reaction (n, alpha) (n,p)., Results were compared with Experimental result from EXFOR DATA library and were in good agreement, the simulation was done in order to ascertain the integrity of the structural material of the reactor and the problem of hydrogen and heluim gas formation on beryllium shim and also the data could be used in event of decommissioning the reactor. this book will help students in reactor engineering , reactor operators under going training in reactor management,and reactor operators.modern rebost operational modal code were still being produced better than EXIFON ,like EMPIRE 3.2, TALLY.
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