EPJ Web of Conferences
Volume 42, 2013WONDER-2012 – 3rd International Workshop On Nuclear Data Evaluation for Reactor applications
|Number of page(s)||7|
|Published online||18 March 2013|
Verification of Neutron Data for Main Reactor Materials from RUSFOND Library based on Integral Experiments
IPPE, Obninsk, Russia 249033
a e-mail: firstname.lastname@example.org
In this work the modern state of the library of evaluated nuclear data files RUSFOND for the main reactor materials, U235, U238, Pu239, Fe, Cr, Ni, Na, Pb, etc., is given. Calculations are performed and comparison with experimental data is done for the following characteristics: (i) Removal cross-sections under the threshold of fission of U-238 etc… (ii) Average cross-sections with different standard neutron fission spectra; (iii) Criticality of fast uranium and plutonium systems. Calculations are performed using continuous energy cross-sections and a Monte-Carlo code.
© Owned by the authors, published by EDP Sciences, 2013
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 2.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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