A statistical sampling method for uncertainty analysis with SCALE and XSUSA

ML Williams, G Ilas, MA Jessee, BT Rearden… - Nuclear …, 2013 - Taylor & Francis
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 …

PSI Methodologies for Nuclear Data Uncertainty Propagation with CASMO‐5M and MCNPX: Results for OECD/NEA UAM Benchmark Phase I

W Wieselquist, T Zhu, A Vasiliev… - … and Technology of …, 2013 - Wiley Online Library
Capabilities for uncertainty quantification (UQ) with respect to nuclear data have been
developed at PSI in the recent years and applied to the UAM benchmark. The guiding …

Decay heat uncertainty for BWR used fuel due to modeling and nuclear data uncertainties

G Ilas, H Liljenfeldt - Nuclear Engineering and Design, 2017 - Elsevier
Abstract Characterization of the energy released from radionuclide decay in nuclear fuel
discharged from reactors is essential for the design, safety, and licensing analyses of used …

Uncertainty quantification of LWR core characteristics using random sampling method

A Yamamoto, K Kinoshita, T Watanabe… - Nuclear Science and …, 2015 - Taylor & Francis
Uncertainties of various neutronics characteristics in commercial boiling water reactor
(BWR) and pressurized water reactor (PWR) cores due to cross-section covariance are …

Analysis of Reactor Simulations Using Surrogate Models.

A Yankov - 2015 - deepblue.lib.umich.edu
The relatively recent abundance of computing resources has driven computational scientists
to build more complex and approximation-free computer models of physical phenomenon …

A Two‐Step Approach to Uncertainty Quantification of Core Simulators

A Yankov, B Collins, M Klein, MA Jessee… - … and Technology of …, 2012 - Wiley Online Library
For the multiple sources of error introduced into the standard computational regime for
simulating reactor cores, rigorous uncertainty analysis methods are available primarily to …

[PDF][PDF] Nuclear data uncertainty propagation in a lattice physics code using stochastic sampling

W Wieselquist, A Vasiliev… - Proceedings of the …, 2012 - researchgate.net
ABSTRACT A methodology is presented for “black box” nuclear data uncertainty
propagation in a lattice physics code using stochastic sampling. The methodology has 4 …

Theoretical Development of Cross Section Uncertainty Library for Core Simulators

D Huang, HS Abdel-Khalik - Journal of Nuclear …, 2020 - asmedigitalcollection.asme.org
The current regulatory process allows for the use of models employing realistic assumptions
as opposed to conservative bounding approaches, requiring a concerted use of best …

Correlation for U-Pu in the thermal and resonance neutron range via integral information

D Rochman, A Vasiliev, H Ferroukhi… - … Physical Journal Plus, 2019 - epjplus.epj.org
This paper presents an application of the Backward-Forward Monte Carlo (BFMC) method
using measured critical boron concentrations for a specific PWR cycle. The considered prior …

Presentation and Discussion of the UAM/Exercise I‐1b:“Pin‐Cell Burn‐Up Benchmark” with the Hybrid Method

O Cabellos - Science and Technology of Nuclear Installations, 2013 - Wiley Online Library
The aim of this work is to present the Exercise I‐1b “pin‐cell burn‐up benchmark” proposed
in the framework of OECD LWR UAM. Its objective is to address the uncertainty due to the …