Update of ENDL U(n,2n), U(n,gamma), U(n,f) Evaluations [electronic resource].
Published
Washington, D.C. : United States. Dept. of Energy, 2004. Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
The authors are in the re-evaluating of all the actinide cross section evaluations in LLNL's ENDL database, starting with uranium and focusing on inventory changing reactions. This article describes their first serious pass at updating the uranium cross section data, including estimates of cross section uncertainties. Furthermore, they are developing new tools to automate the re-evaluation and this article contains some preliminary results from these codes, namely the ²³⁵U(n, 2n) and ²³⁸U(n, 2n) evaluations.