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International Journal of Energy Research, Volume 2024, Issue 1, 2024.Data assimilation (DA) was revealed as a highly efficient approach to enhance the prediction’s accuracy, demonstrating the reliability of the simulation through uncertainty quantification analysis. However, in the numerical simulations, most of the tasks are highly nonlinear relationships between the parameters that directly affect the efficiency of ...
Nguyen Huu Tiep +7 more
wiley +1 more source
Worst‐Case Accident Analysis of Accident Tolerant Fuel in NuScale Using RELAP5/MOD3‐Based Code
International Journal of Energy Research, Volume 2024, Issue 1, 2024.Research in nuclear engineering focusses on improving the safety of light water reactors (LWRs), driven by accidents like Fukushima in 2011. The severity of this accident was a result of active cooling system failures and cladding material oxidation resulting in hydrogen explosions.
Willem Zuidersma +3 more
wiley +1 more source
SCDAP/RELAP5 independent peer review [PDF]
, 1993 The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light-water-reactor coolant systems during severe accidents. The newest version of the code is SCDAP/RELAP5/MOD3. The US Nuclear Regulatory Commission (NRC) decided that there was a need for a broad technical review of the code by recognized experts to determine overall ...
Corradini +20 more
openaire +2 more sources
RELAP5-3D Code Validation for RBMK Phenomena [PDF]
, 1999 The RELAP5-3D thermal-hydraulic code was assessed against Japanese Safety Experiment Loop (SEL) and Heat Transfer Loop (HTL) tests. These tests were chosen because the phenomena present are applicable to analyses of Russian RBMK reactor designs. The assessment cases included parallel channel flow fluctuation tests at reduced and normal water levels, a ...
openaire +4 more sources
Modeling Moving Systems with RELAP5-3D
Nuclear Science and Engineering, 2016 RELAP5-3D is typically used to model stationary, land-based reactors. However, it can also model reactors in other inertial and accelerating frames of reference. By changing the magnitude of the gravitational vector through user input, RELAP5-3D can model reactors on a space station or the moon.
G. L. Mesina +3 more
openaire +2 more sources
Benchmark Comparison of Experimental Data with Thermal-Hydraulic Codes RELAP5-3D and TRACE for a RIA Transient Scenario [PDF]
, 2020 Wade Marcum +4 more
openalex +1 more source
Liquid metal cooled fast reactor thermal hydraulic research development: A review. [PDF]
Heliyon, 2023 Agbevanu KT +3 more
europepmc +1 more source
Modifications to the VV PHTS RELAP5 Model [PDF]
, 2011 Modifications and improvements to a previous RELAP5 model of the Vacuum Vessel Primary Heat Transfer System are described in this report. The modifications were new pump models, a new steam pressurizer, new coolant water control systems, additional pipe structures, and reduction of the pulse power to 6 MW.
openaire +2 more sources
An Interpretable Time Series Data Prediction Framework for Severe Accidents in Nuclear Power Plants. [PDF]
Entropy (Basel), 2023 Fu Y, Zhang D, Xiao Y, Wang Z, Zhou H.
europepmc +1 more source
An open time-series simulated dataset covering various accidents for nuclear power plants. [PDF]
Sci Data, 2022 Qi B +5 more
europepmc +1 more source