Since 1978 Published in Sarov (Arzamas-16), Nizhegorodskaya oblast
RUSSIAN FEDERAL NUCLEAR CENTER -
ALL-RUSSIAN RESEARCH INSTITUTE OF EXPERIMENTAL PHYSICS
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ON THE QUESTION OF SLOW NEUTRON SCATTERING DESCRIPTION IN ENDF
D. G. Modestov VANT. Ser.: Mat. Mod. Fiz. Proc 2008. Вып.3. С. 47-54.
The suggested IAEA ENDF data libraries are, perhaps, the most widely used in neutron moderation transport problems. Still there is a number of errors in the format description, which could result in unphysical dependence of the scattering cross-section on the energy. The paper considers the analysis of one of these errors concerning the representation of scattering law in approximation of instantaneous collision.
INSTANTANEOUS COLLISION APPROXIMATION FOR SIMULATION OF SLOW NEUTRON TRANSPORT
D. G. Modestov VANT. Ser.: Mat. Mod. Fiz. Proc 2008. Вып.3. С. 55-67.
The estimated ENDF nuclear data libraries are often used in problems in which the low-energy neutron transport plays an important role. In this case, the incoherent inelastic scattering reaction is, perhaps, the most complicated for realization among the reactions typical of thermal neutrons. Here, the representation of scattering law in the instantaneous collision approximation is the most frequently used yet the least investigated representation. Given here is the explicit form of the integrated cross-section in this approximation, and sampling algorithm of scattering parameters required for transport problem solution using statistical simulation techniques. The comparison with BRAND technique is given.
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