Results 141 to 150 of about 1,865 (177)
Some of the next articles are maybe not open access.
RELAP5 code theoretical simulation of the experiment of natural circulation STAR
International Journal of Nuclear Energy Science and Technology, 2023Gaianê Sabundjian +2 more
exaly +2 more sources
INVESTIGATION ON TWO-PHASE FLOW INSTABILITIES WITH RELAP5 CODE
, 2012 During the operation of any kind of industrial power plant, the stability of the process is of primary importance since it could directly affect the safety on the performance of the system. A very important phenomenon, which affects many industrial applications, is the stability of two-phase flow in boiling channels.
CRISTOFANO, LUCA +3 more
openaire +2 more sources
Scaling of the accuracy of the Relap5/mod2 code
Nuclear Engineering and Design, 1993Abstract This paper presents an attempt to derive uncertainty values in the prediction of BWR and PWR transient scenarios. The small break LOCA counterpart tests performed in the BWR simulators Piper-one, Fist and Rosa-III, and natural circulation experiments performed in the PWR simulators Lobi, Spes and Lstf, constitute the basis of the activity ...
R. Bovalini, F. D'Auria
openaire +1 more source
Coupling of RELAP5-SCDAP MOD4.0 and Neutronic Codes
Volume 6B: Energy, 2015High-fidelity and accurate nuclear system codes play a key role in the design and analysis of complex nuclear power plants, which consist of multiple subsystems, such as the reactor core (and its fuel, burnable poisons, control elements, etc.), the reactor internal structures, the vessel, and the energy conversion subsystem and beyond to grid demand ...
Victor Martinez-Quiroga +4 more
openaire +1 more source
Modeling TBM Components by Using RELAP5 Code
Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, 2013RELAP5 is a best estimate system code suitable for the analysis of all transients and postulated accidents in Light Water Reactor systems. It was usually used to solve plant thermal-hydraulic problems on system scale. RELAP5 was used to study thermal-hydraulic behavior on component level in this paper.
Yaoli Zhang, Tianji Peng
openaire +1 more source
On the use of RELAP5-3D as a subchannel analysis code
Nuclear Engineering and Design, 2010Abstract The capabilities of the RELAP5-3D code to perform subchannel analyses in sodium-cooled fuel assemblies were evaluated. The motivation was the desire to analyze fuel assemblies with traditional (solid pins) as well as non-traditional (e.g., annular pins with internal cooling, bottle-shape) geometries.
Matthew Memmott +2 more
openaire +1 more source
TMI-2 Accident Analysis with SCDAP/RELAP5 Code
, 1999 Analysis of the TMI-2 accident has been performed using the SCDAP/RELAP5/MOD3.2 system code, which is being developed by INEEL for the U.S. NRC. The nodalization of the TMI-2 plant included a detailed modeling of the primary coolant system with the reactor pressure vessel, the two coolant loops with once-through steam generators and main coolant pumps,
Bandini, G.
openaire +2 more sources
Development of a thermal–hydraulic system code for simulators based on RELAP5 code
Nuclear Engineering and Design, 2005Abstract A thermal–hydraulic system code for simulators, RELAPSIM, was developed at NSSE based on RELAP5. The development procedure consists of three major parts. Firstly, time control function was added into the code to meet real-time calculation needs.
Meng Lin +4 more
openaire +1 more source
The RELAP5-FORCE MOD2 Code, A Hydrodynamic Forcing Function Calculation Version of RELAP5
Nuclear Technology, 1990A version of the RELAP/MOD2 code has been developed to allow the direct calculation of hydrodynamic piping load histories. The code allows the calculation of piping forcing functions to evaluate the transient thermofluid conditions. A description of this code, RELAP5-FORCE MOD2 is provided.
openaire +1 more source
RELAP5-3D Code Validation for RBMK-1500 Reactors
12th International Conference on Nuclear Engineering, Volume 3, 2004This paper deals with RELAP5-3D code validation through the modeling of RBMK-1500 specific transients taking place at Ignalina NPP. A successful best estimate RELAP5-3D model of the INPP RBMK-1500 reactor has been developed and validated against real plant data.
Evaldas Bubelis +2 more
openaire +1 more source