Program - Brookhaven National Laboratory
Program - Brookhaven National Laboratory
Program - Brookhaven National Laboratory
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DC 2 4:00 PM<br />
Improved Capture Gamma-Ray Libraries for Nonproliferation Applications<br />
B. W. Sleaford, L.A. Bernstein, J.E. Escher, W.E. Ormand, N.C. Summers, Lawrence Livermore <strong>National</strong><br />
<strong>Laboratory</strong>, Livermore, CA 94551,. M.S. Basunia, R.B. Firestone, A.M. Hurst, A.M. Rogers, Lawrence<br />
Berkeley <strong>National</strong> <strong>Laboratory</strong>, Berkeley, CA 94720. K. AbuSaleem, Department of Physics, The<br />
University of Jordan, Amman, Jordan. F. Becvár, M. Krticka, Charles University in Prague, Faculty of<br />
Mathematics and Physics, Czech Republic. T. Belgya, L. Szentmiklosi, Centre for Energy Research,<br />
Hungarian Academy of Sciences, Budapest, Hungary. H. Choi, Seoul <strong>National</strong> University, Korea. Zs.<br />
Revay, Forschungsneutronenquelle Heinz Maier-Leibnitz (FRM II), Technische Universität, Munich,<br />
Germany. Ch. Genreith, M. Rossbach, Institute for Energy and Climate Research, IEK-6,<br />
Forschungszentrum, Juelich, Germany. F. Gunsing, CEA Saclay, Gif-sur-Yvette, France.<br />
The neutron-capture reaction is of fundamental use in identifying and analyzing the gamma-ray spectrum<br />
from an unknown object as it gives unambiguous information on which isotopes are absorbing the neutrons.<br />
There are known data gaps in the Evaluated Nuclear Data File (ENDF) libraries used by transport codes<br />
which are critical to a range of nonproliferation applications, particularly the actinides. The Evaluated<br />
Gamma-ray Activation File (EGAF) is a thermal neutron-capture database of discrete-line spectra and<br />
cross sections for over 260 isotopes measured at the Budapest and Munich Reactors (FRM II). For medium<br />
to heavy nuclei, the unresolved quasi continuum part of the gamma cascades are not experimentally<br />
available and is modeled in the evaluation process using the statistical nuclear structure code DICEBOX<br />
developed at Charles University in Prague. ENDF libraries require gamma-ray production cross sections<br />
for neutron energies up to 20 MeV and accordingly, we plan to continue the Dicebox approach through<br />
the resolved resonance region where spin and parity information is partially known. This modeling can be<br />
benchmarked with gamma spectra from neutron time of flight experiments although data exists only for a<br />
limited number of isotopes. In the unresolved resonance and high energy regions, we are applying a modified<br />
version of DICEBOX (CASINO) which starts cascades from a range of capture states and accounts for<br />
gamma and neutron output channels. Additionally, we are using Hauser-Feshbach modeling developed at<br />
Lawrence Livermore <strong>National</strong> <strong>Laboratory</strong> to predict the cross sections of capture gamma spectra in regions<br />
where multiple competing output channels are open. This combination of experiment and modeling is being<br />
used to improve the neutron-capture data libraries used by the nuclear nonproliferation, engineering and<br />
science communities. This work is performed in part under the auspices of the U.S. Department of Energy<br />
by Lawrence Livermore <strong>National</strong> <strong>Laboratory</strong> under Contract DE-AC52-07NA27344.<br />
DC 3 4:20 PM<br />
Fission Product Neutron Cross Section Library and its Reliability Assessment<br />
Jing Qian, Zhengjun Sun, Tinjin Liu<br />
China Nuclear Data Center, China Institute of Atomic Energy<br />
A complete library of neutron cross section data has been developed for fission product nuclides. It contains<br />
the data for 1121 fission product nuclides from 66 Ti to 172 Hf, atomic numbers 22 to 72, where involves<br />
a lot of very short-lived radioactive ones. The data were taken from better evaluated data libraries of<br />
ENDF/B-VII.0, EAF-2010 and TENDL-2010 or calculated by model theoretical computing code TALYS.<br />
The results for dominant major reaction channels up to 20 MeV were presented, which gives not only<br />
the cross section at mono-energies but also the Maxwell and fission spectrum average ones. Cross section<br />
reliability assessment has been done by comparing with experimental data and statistical analysis of cross<br />
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