Challenges and progress of uncertainty analysis for the pebble-bed high-temperature gas-cooled reactor

J Guo, Y Wang, H Zhang, M Cui, F Li - Progress in Nuclear Energy, 2021 - Elsevier
There has been increasing demand for uncertainty quantification (UQ) in the nuclear
engineering community. Thus far, most uncertainty analyses have focused on light water …

FERMI: fusion energy reactor models integrator

V Badalassi, A Sircar, JM Solberg, JW Bae… - Fusion Science and …, 2023 - Taylor & Francis
Abstract The Fusion Energy Reactor Models Integrator (FERMI) is an integrated simulation
environment under development for the coupled simulation of the plasma, first wall, and …

Improved generalized perturbation theory method for sensitivity analysis of generalized response function

G Shi, C Jia, X Guo, K Li, K Wang, S Huang… - Progress in Nuclear …, 2021 - Elsevier
Sensitivity and uncertainty analyses of generalized response functions are essential for
nuclear designs because they provide useful information about how changes in the input …

Development of a reduced order model for fuel burnup analysis

C Castagna, M Aufiero, S Lorenzi, G Lomonaco… - Energies, 2020 - mdpi.com
Fuel burnup analysis requires a high computational cost for full core calculations, due to the
amount of the information processed for the total reaction rates in many burnup regions …

Nuclear data sensitivity and uncertainty analysis of effective neutron multiplication factor in various MYRRHA core configurations

P Romojaro, F Álvarez-Velarde, I Kodeli… - Annals of Nuclear …, 2017 - Elsevier
A sensitivity and uncertainty analysis was carried out to estimate the uncertainty in the
neutron multiplication factor k eff and to identify the most important nuclear data for neutron …

Utilization of ACE nuclear data file toolkit ACEtk to calculate relative sensitivity coefficients of point-kinetics parameters

N Kleedtke, W Haeck, J Hutchinson - Annals of Nuclear Energy, 2023 - Elsevier
Sensitivity and uncertainty methods are quintessential for nuclear criticality safety and
experiment design. This type of analysis relies on calculations of sensitivity coefficients; …

Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT

JD Bess, NE Woolstenhulme, CB Jensen… - Annals of Nuclear …, 2019 - Elsevier
Abstract The Transient Reactor Test facility (TREAT) was constructed in the late 1950s,
provided thousands of transient irradiations before being placed in standby in 1994, and …

[HTML][HTML] Irradiated fuel salt data library for a molten salt reactor produced with Serpent2 and SOURCES 4C codes

V Mishra, Z Elter, E Branger, S Grape, S Mirmiran - Data in Brief, 2024 - Elsevier
This paper describes the creation and description of a nuclear fuel isotopics dataset for
irradiated fuel salt from a Molten Salt Reactor (MSR). The dataset has been created using …

Best‐Estimate Plus Uncertainty Framework for Multiscale, Multiphysics Light Water Reactor Core Analysis

J Hou, M Avramova, K Ivanov - Science and Technology of …, 2020 - Wiley Online Library
Tremendous work has been done in the Light Water Reactor (LWR) Modelling and
Simulation (M&S) uncertainty quantification (UQ) within the framework of the Organization …

Note on the potential to increase the accuracy of source term calculations for spent nuclear fuel

M Seidl, P Schillebeeckx, D Rochman - Frontiers in Energy Research, 2023 - frontiersin.org
The accuracy of source term predictions is an important factor which determines the
efficiency of interim and final storage of spent nuclear fuel. To minimize the required number …