ENDF/B-VII. 1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data
The ENDF/B-VII. 1 library is our latest recommended evaluated nuclear data file for use in
nuclear science and technology applications, and incorporates advances made in the five …
nuclear science and technology applications, and incorporates advances made in the five …
A statistical sampling method for uncertainty analysis with SCALE and XSUSA
A new statistical sampling sequence called Sampler has been developed for the SCALE
code system. Random values for the input multigroup cross sections are determined by …
code system. Random values for the input multigroup cross sections are determined by …
Sensitivity and uncertainty analysis capabilities and data in SCALE
BT Rearden, ML Williams, MA Jessee… - Nuclear …, 2011 - Taylor & Francis
In SCALE 6, the T ools for S ensitivity and UN certainty A nalysis M ethodology I
mplementation (TSUNAMI) modules calculate the sensitivity of keff or reactivity differences to …
mplementation (TSUNAMI) modules calculate the sensitivity of keff or reactivity differences to …
Calculations of Maxwellian-averaged cross sections and astrophysical reaction rates using the ENDF/B-VII. 0, JEFF-3.1, JENDL-3.3, and ENDF/B-VI. 8 evaluated …
We have calculated the Maxwellian-averaged cross sections and astrophysical reaction
rates of the stellar nucleosynthesis reactions (n, γ),(n, fission),(n, p),(n, α), and (n, 2n) using …
rates of the stellar nucleosynthesis reactions (n, γ),(n, fission),(n, p),(n, α), and (n, 2n) using …
Neutron thermal cross sections, Westcott factors, resonance integrals, Maxwellian averaged cross sections and astrophysical reaction rates calculated from the ENDF …
We present calculations of neutron thermal cross sections, Westcott factors, resonance
integrals, Maxwellian-averaged cross sections and astrophysical reaction rates for 843 …
integrals, Maxwellian-averaged cross sections and astrophysical reaction rates for 843 …
Modeling of the molten salt reactor experiment with SCALE
A SCALE model was developed for the Molten Salt Reactor Experiment (MSRE) benchmark
that was recently added to the International Handbook of Evaluated Reactor Physics …
that was recently added to the International Handbook of Evaluated Reactor Physics …
Measurement of the neutron flux at spallation sources using multi-foil activation
Activation analysis is used in this work to measure the flux of a fast neutron beamline at a
spallation source over a wide energy spectrum, extending from thermal to hundreds of MeV …
spallation source over a wide energy spectrum, extending from thermal to hundreds of MeV …
Nuclear data uncertainties for typical LWR fuel assemblies and a simple reactor core
The impact of the current nuclear data library covariances such as in ENDF/B-VII. 1, JEFF-
3.2, JENDL-4.0, SCALE and TENDL, for relevant current reactors is presented in this work …
3.2, JENDL-4.0, SCALE and TENDL, for relevant current reactors is presented in this work …
Comparison of nuclear data uncertainty propagation methodologies for PWR burn-up simulations
CJ Diez, O Buss, A Hoefer, D Porsch… - Annals of Nuclear Energy, 2015 - Elsevier
Several methodologies using different levels of approximations have been developed for
propagating nuclear data uncertainties in nuclear burn-up simulations. Most methods fall …
propagating nuclear data uncertainties in nuclear burn-up simulations. Most methods fall …
[HTML][HTML] Nuclear data uncertainty and sensitivity analysis with XSUSA for fuel assembly depletion calculations
W Zwermann, A Aures, L Gallner, V Hannstein… - Nuclear Engineering …, 2014 - Elsevier
Uncertainty and sensitivity analyses with respect to nuclear data are performed with
depletion calculations for BWR and PWR fuel assemblies specified in the framework of the …
depletion calculations for BWR and PWR fuel assemblies specified in the framework of the …