Results 81 to 90 of about 5,558 (186)
Time‐Series Forecasting of a Typical PWR Undergoing Large Break LOCA
Science and Technology of Nuclear Installations, Volume 2024, Issue 1, 2024.In this work, a machine learning (ML) metamodel is developed for the time‐series forecasting of a typical nuclear power plant response undergoing a loss of coolant accident (LOCA). The plant model of choice is based on the APR1400 nuclear reactor. The key systems and components of APR1400 relevant to the investigated scenario are modelled using the ...
Michal Kaminski +2 more
wiley +1 more source
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
Core Flow Distribution from Coupled Supercritical Water Reactor Analysis
Science and Technology of Nuclear Installations, 2014 This paper introduces an extended code package PARCS/RELAP5 to analyze steady state of SCWR US reference design. An 8 × 8 quarter core model in PARCS and a reactor core model in RELAP5 are used to study the core flow distribution under various steady ...
Po Hu, Paul P. H. Wilson
doaj +1 more source
Nuclear Engineering and Technology, 2018 An experiment was performed for the OECD/NEA ROSA-2 Project with the large-scale test facility (LSTF), which simulated a steam generator tube rupture (SGTR) accident due to a double-ended guillotine break of one of steam generator (SG) U-tubes with ...
Takeshi Takeda
doaj +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
Science and Technology of Nuclear Installations, 2010 The Institute of Neutron Physics and Reactor Technology (INR) is involved in the qualification of coupled codes for reactor safety evaluations, aiming to improve their prediction capability and acceptability.
V. Sánchez +3 more
doaj +1 more source
Simulation of rod ejection accident byPARCS code [PDF]
, 2015 This paper describes reactor core model used for simulating REA. The model was designed in PARCS utilizing graphical interface SNAP. The data for model were given from benchmark NEACPR L-335.
Matějková, J.
core
Analysis of Density Wave Oscillations in Helically Coiled Tube Once-Through Steam Generator
Science and Technology of Nuclear Installations, 2016 Helically coiled tube Once-Through Steam Generator (H-OTSG) is one of the key equipment types for small modular reactors. The flow instability of the secondary side of the H-OTSG is particularly serious, because the working condition is in the range of ...
Junwei Hao +7 more
doaj +1 more source
Thermal-hydraulic Fortran program for steady-state calculations of plate-type fuel research reactors [PDF]
, 2008 The safety assessment of research and power reactors is a continuous process covering their lifespan and requiring verified and validated codes. Power reactor codes all over the world are well established and qualified against real measuring data and ...
Khedr Ahmed
core +1 more source
RELAP5/MOD3.3 Analysis of the Loss of External Power Event with Safety Injection Actuation
Science and Technology of Nuclear Installations, 2018 The code assessment typically comprises basic tests cases, separate effects test, and integral effects tests. On the other hand, the thermal hydraulic system codes like RELAP5/MOD3.3 are primarily intended for simulation of transients and accidents in ...
Andrej Prošek, Marko Matkovič
doaj +1 more source