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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
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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
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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.
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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
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RELAP5/Mod3.2 - Quabox/Cubbox-Hyca Coupled Code
1997QUABOX/CUBBOX-HYCA is well known 3D coarse mesh neutron kinetics code developed in GRS Garching. It is coupled to different code systems and used for calculation of different types of reactors. Objective of this work is to develop code, based on RELAP5/mod3.2 and QUABOX/CUBBOX-HYCA, for class of transients characterized by spatial dependence in the ...
Grgić, Davor +6 more
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Thermal Hydraulics of Accelerator-Driven System Using RELAP5 Code
Journal of Nuclear Engineering and Radiation Science, 2015A lead–bismuth eutectic (LBE)-cooled accelerator-driven system (ADS) of 30 MeV and 0.5 mA proton beam has been simulated. The performance of this 15-kW ADS has been analyzed for three coolants (LBE, air, and water), all under variable and constant heat loads using the thermal hydraulic code RELAP5/Mod4.0. Steady-state simulation results for temperature
Indu Kumari, Ashok Khanna
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Foreword: Special Issue on the RELAP5-3D Computer Code
Nuclear Science and Engineering, 2016(2016). Foreword: Special Issue on the RELAP5-3D Computer Code. Nuclear Science and Engineering: Vol. 182, No. 1, pp. iii-iii.
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SPES-99 IBLOCA Analysis with the RELAP5 Mod 3.2 Code
2000SPES is an experimental facility which allows the assessment of thermalhydraulic codes through the simulation of a wide range of physical phenomena characterising different accident scenarios in PWRs. In 1999, in view of a possible proposal for an international cooperative programme, ENEA provided the SIET company with limited funding to restore the ...
D'AURIA, FRANCESCO SAVERIO +5 more
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QUENCH-11 Experiment Analysis with RELAP5/SCDAPSIM Code
2008The QUENCH program is a research program running at Karlsruhe Research Center (FZK – Forschungszentrum Karlsruhe) that is focused on the investigation of cladding behaviour and hydrogen source term following the water injection in the uncovered core of a light water reactor (LWR).
Šadek, Siniša +2 more
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