Results 101 to 110 of about 362 (143)
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Comparison of MYRRHA RELAP5 MOD 3.3 and RELAP5-3D Models on Steady State and PLOF Transient

Nuclear Technology, 2016
AbstractThe MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) project aims at the construction of a pool-type subcritical accelerator-driven system that could also operate a...
D. Castelliti, T. Hamidouche
openaire   +1 more source

RELAP5 Two-Fluid Model

2016
In this chapter, we consider the full 1D TFM of RELAP5 for bubbly vertical flows and assess its linear stability behavior and material wave propagation capabilities in light of the linear stability analyses of Chap. 5, i.e., the characteristics and the dispersion relation.
Martín López de Bertodano   +3 more
openaire   +1 more source

The RELAP5-FORCE MOD2 Code, A Hydrodynamic Forcing Function Calculation Version of RELAP5

Nuclear Technology, 1990
A 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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Development of Adaptive Sampling Software Based on Relap5

Volume 15: Student Paper Competition, 2022
Abstract The RISMC analysis method is a coupled dynamic safety analysis method that combines deterministic safety analysis and probabilistic safety analysis. It comprehensively simulates the dynamic response process of nuclear power plants under accidents through Monte Carlo sampling and dynamic event tree methods.
Haoyin Chen   +4 more
openaire   +1 more source

RELAP5-3D User Tools

Nuclear Technology, 2016
To support the functionality of RELAP5-3D for best-estimate reactor simulation code, a variety of utility programs were developed at Idaho National Laboratory.
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???????????????????? ???????????? ???????????????????? ???????????????? ???????????? ???????????????????? ???????? RELAP5/MOD3.2 ?????? ?????????????? ?????????????????? ????????-1000 ?????? ?????????????? ?????????????????? ????????????

2018
The paper presents applicability of built-in RELAP5/MOD3.2 cladding deformation model for VVER-1000 fuel with cladding of Zr+1 % Nb alloy. Experimental data and simplified model of fuel assembly channel of the core are used for this purpose. The model applicability is tested for the hot channel blockage after cladding swelling and rupture in the ...
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RELAP5 investigation on subchannel flow instability

Kerntechnik, 2016
Abstract Two-phase flow instability is a vitally important area of study for a large number of industrial systems. Density Wave Oscillation (DWO) is the most common type of flow instability caused by the change in flow rate or power in boiling systems.
S. Wang, B.-W. Yang, A. Liu, X. Liu
openaire   +1 more source

Scaling of the accuracy of the Relap5/mod2 code

Nuclear Engineering and Design, 1993
Abstract 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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Modification of the Reflood Model in RELAP5/MOD3.1

Nuclear Technology, 1998
A few features of the reflood model in RELAP5/ MOD3.1 have been modified to improve the unrealistic prediction results of the model. In the new method, the modified Zuber pool boiling critical heat flux correlation is adopted in the range of mass flux G < 150 kg/ m 2 . s. The new criterion for reflood drop size, which is characterized by the use of We
Hae Yong Jeong, Hee Cheon No
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Recent Applications of RELAP5-3D at GRNSPG

2012
CNA2 : FSAR activities Standard Consolidated Reference Experimental Database MASLWR benchmark OECD benchmarks CHF calculation in low mass flux condition Turbulence effects in Relap5 ...
D'AURIA, FRANCESCO SAVERIO   +9 more
openaire   +2 more sources

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