Update of ENDL U(n,2n), U(n,gamma), U(n,f) Evaluations
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 {sup 235}U(n, 2n) and {sup 238}U(n, 2n) evaluations.
- Research Organization:
- Lawrence Livermore National Lab., Livermore, CA (US)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 15009784
- Report Number(s):
- UCRL-TR-202393
- Country of Publication:
- United States
- Language:
- English
Similar Records
Reevaluation of ENDL of sigma(n,f) and anti nu/sub p/ for /sup 235/U and /sup 239/Pu from 100 keV to 20 MeV
Calculation of 239Pu(n,2n) Cross Section by the Subtraction and the Ratio Methods
Updated ENDL99 Cross Sections for U(n.y) and U(n,f)
Technical Report
·
Sat Dec 31 19:00:00 EST 1983
·
OSTI ID:5460471
Calculation of 239Pu(n,2n) Cross Section by the Subtraction and the Ratio Methods
Technical Report
·
Thu Sep 28 00:00:00 EDT 2000
·
OSTI ID:792742
Updated ENDL99 Cross Sections for U(n.y) and U(n,f)
Technical Report
·
Tue May 07 00:00:00 EDT 2002
·
OSTI ID:15004658