Results 61 to 70 of about 2,939 (182)
Opposing Mixed Convection Heat Transfer for Turbulent Single‐Phase Flows
International Journal of Energy Research, Volume 2024, Issue 1, 2024.Convection, wherein forced and natural convections are prominent, is known as mixed convection. Specifically, when a forced convection flow is downward, this flow is called opposing flow. The objectives of this study are to gain a comprehensive understanding of opposing flow mixed convection heat transfer and to establish the prediction methodology by ...
Kosuke Motegi +5 more
wiley +1 more source
A study of the dispersed flow interfacial heat transfer model of RELAP5/MOD2.5 and RELAP5/MOD3
, 1995 The model of interfacial heat transfer for the dispersed flow regime used in the RELAP5 computer codes is investigated in the present paper. Short-transient calculations of two low flooding rate tube reflooding experiments have been performed, where the hydraulic conditions and the heat input to the vapour in the post-dryout region were controlled for ...
Andreani, M, Analytis, G T, Aksan, S N
openaire +4 more sources
SCDAP/RELAP5/MOD2 code manual [PDF]
, 1990 This report describes the materials properties correlations and computer subcodes (MATPRO) developed for use with various light water reactor (LWR) accident analysis computer programs. Formulation of the materials properties are generally semiempirical in nature.
Hohorst +5 more
openaire +2 more sources
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
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
SCDAP/RELAP5/MOD2 code manual [PDF]
, 1989 The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, and the fission products and aerosols in the system during a severe accident transient as well as large and small break loss-of ...
Allison, C. M. +13 more
openaire +6 more sources
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
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
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