Angular and energy distributions of γ-rays scattered in iron and lead

Criterion for the optimal choice of delayed-neutron data

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A new approach for solving the important problem of choosing the optimal delayed-neutron data (number of groups, fractions β j , energy spectra χ j , decay constants λ j of precursors) for a particular reactor is proposed [1][2][3][4][5][6][7][8][9][10][11].The evolution of the neutron flux in a reactor is described by the direct kinetic equation [5][6][7][8]

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“…The evolution of the neutron flux in a reactor is described by the direct kinetic equation [5][6][7][8] …”

“…The corresponding inverse equation of kinetics (or the inverse solution of the equation of kinetics (ISEK [5]) for determining the reactivity ρ/b in the units b = β eff assumes the form (2) where (3) (,) denotes an integral over all values of the variables x, E, and Ω which are examined; ρ = 1 -1/k eff is the reactivity; ψψ * ≥ 0 is the solution of the conditionally critical equations…”

“…M * and F * are the conjugates of the operators M and F. See [5][6][7][8] for other forms of the method. Equation (2) is the exact solution in the sense that it gives the exact value of the reactivity if the exact solutions of Eqs.…”