Results 141 to 150 of about 2,939 (182)

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
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, William Fullmer, Alejandro Clausse, Victor H. Ransom   +3 more
openaire   +1 more source

???????????????????? ???????????? ???????????????????? ???????????????? ???????????? ???????????????????? ???????? 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 ...
openaire   +2 more sources

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
openaire   +1 more source

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

Coupling of RELAP5-SCDAP MOD4.0 and Neutronic Codes

Volume 6B: Energy, 2015
High-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, Sabahattin Akbas, Fatih Aydogan, Abderrafi M. Ougouag, Chris Allison   +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, 2013
RELAP5 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

One-Dimensional Diffusion Theory Kinetics in RELAP5

Nuclear Science and Engineering, 1995
A one-dimensional (axial) space-time reactor kinetics capability has been developed for the well-known RELAP5 thermohydraulic systems code for modeling the behavior of nuclear power plants. The method is based on the analytic nodal method with a novel technique for performing the temporal integration over relatively large time steps.
William K. Terry, David W. Nigg
openaire   +1 more source

On the Subcooled Critical Flow Model in RELAP5/MOD3

Nuclear Technology, 1996
An analysis of an anomaly in the subcooled critical flow model in the RELAP5/MOD3 computer code is presented. Specifically, the code produces a discontinuity in going from unchoked subcooled liquid flow (i.e., subsonic flow) to subcooled choked flow (i.e., sonic flow). The same anomaly has been reported elsewhere.
W. S. Yeung, J. Shirkov
openaire   +1 more source

?????????????????? ?????????????????????????????????????? ???????????? ???????????????? ????????-1000 ?????? ?????????????????????????? ???????? RELAP5/MOD3.2 ???? ???????????? ?????????????? ?????????????????? ?????????????? ????????????????

2016
The WWER-1000 reactor model for RELAP5/mod3.2 computer code is validated. The model includes detailed modeling of the downcomer by dividing it azimuthally into 20 vertical channels with crossflow junctions. The measured parameters for the failure of the Rivne-3 pressurizer safety valve to close are used as experimental data.
openaire   +3 more sources