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 ...
M Andreani, G T Analytis, S N Aksan
openaire +2 more sources
Basis for Coupled 3-D Neutronics-Thermal-Hydraulics [PDF]
, 2008 The purpose of this seminar is first to discuss the basis of the coupling between 3-D Neutron- Kinetics and Thermal-Hydraulics codes, including the control and 3-D variables to interchange, the transform of the 3-D NK and TH core nodalizations, and the ...
Aragonés Beltrán, José María
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Analysis on Non-Uniform Flow in Steam Generator During Steady State Natural Circulation Cooling [PDF]
, 2007 Investigation on non uniform flow behavior among U-tube in steam generator during natural circulation cooling has been conducted using RELAP5. The investigation is performed by modeling the steam generator into multi channel models, i.e.
Susyadi, S. (Susyadi), Yonomoto, T. (T)
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Analisi di un evento di PTS originato da un incidente di tipo MSLB in un impianto nucleare WWER-1000/320 condotta mediante i codici accoppiati Relap5, Trio_U e Ansys [PDF]
, 2003 Titolo della tesi: “Analisi di meccanica della frattura del vessel di un impianto nucleare WWER-1000/320 condotta mediante i codici accoppiati Relap5, Trio_U e Ansys, in caso di un evento di PTS originato da un incidente di tipo MSLB” Riassunto: Il ...
Vettori, Stefano
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Physics Based Model for Cryogenic Chilldown and Loading. Part III: Correlations [PDF]
In this report we discuss the details of the correlations used to recognize flow patterns and predict frictional losses, heat and mass transfer in the cryogenic two phase flow.
Brown, B. +6 more
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First Experience with the Consolidation of WWER Reactor Pressure Vessel Knowledge through a New Method [PDF]
, 2008 One of today¿s activities of the Joint Research Centre¿s (JRC) Institute for Energy (IE) concerns data management and dissemination in nuclear safety. An ¿Online Data & Information Network¿ (ODIN) is set-up, which maintains one document database and four
BRUMOVSKY Milan +3 more
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Forced boiling of nanofluids, effects of contact angle and surface wettability [PDF]
, 2011 This paper was presented at the 3rd Micro and Nano Flows Conference (MNF2011), which was held at the Makedonia Palace Hotel, Thessaloniki in Greece.
3rd Micro and Nano Flows Conference (MNF2011) +4 more
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RELAP5 assessment: LOFT large break L2-5
, 1984 RELAP5 is part of an effort to determine the ability of various systems codes to predict the detailed thermal/hydraulic response of LWRs during accident and off-normal conditions. The RELAP5 code is being assessed at SNLA against test data from various integral and separate effects test facilities.
S Thompson, L Kmetyk
openaire +2 more sources
Investigation of flow and heat transfer in a large-scale spent nuclear fuel cooling pond [PDF]
The recent focus on nuclear power has led to the need for more efficient and economical methods of operating the Spent Nuclear Fuel (SNF) cooling ponds as well as complying with the strict safety and environmental legislations imposed by the IAEA and the
Ramadan, Ahmed Mohamed, Sellafield Ltd
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Steam generator identification using piecewise affine model
Results in Nonlinear Analysis, 2019 The role of steam generators in power plants is to remove the thermal power produced in the first cycle and provide the turbine intake steam. Controlling the steam generator water level has an important role in preventing unwanted turbine trips and ...
Samaneh Sadat Sajjadi, Amin Jajarmi, Ahamad Hajipour
doaj