scholarly journals DRIVERS’ EYE GLANCE TRANSITIONS AND THE IMPLICATIONS ON THE MICROSCOPIC TRAFFIC AND ACCIDENT SIMULATION

Author(s):  
YEEUN KIM ◽  
SEHYUN TAK ◽  
SEONGJIN CHOI ◽  
HWASOO YEO
Keyword(s):  

1981 ◽  
Author(s):  
G. E. Russcher ◽  
L. W. Cannon ◽  
R. L. Goodman ◽  
G. M. Hesson ◽  
L. L. King ◽  
...  


Author(s):  
Eduardo Mario Dias ◽  
Maria Lidia Rebello Pinho Dias Scoton ◽  
Luiz Reis ◽  
Sergio Luiz Pereira


2009 ◽  
Vol 165 (3) ◽  
pp. 293-307 ◽  
Author(s):  
J. P. van Dorsselaere ◽  
C. Seropian ◽  
P. Chatelard ◽  
F. Jacq ◽  
J. Fleurot ◽  
...  


2014 ◽  
Vol 446 (1-3) ◽  
pp. 73-80 ◽  
Author(s):  
Mária Sudolská ◽  
Laurent Cantrel ◽  
Šimon Budzák ◽  
Ivan Černušák


2021 ◽  
Vol 13 (14) ◽  
pp. 7964
Author(s):  
Alain Flores y Flores ◽  
Danilo Ferretto ◽  
Tereza Marková ◽  
Guido Mazzini

The severe accident integral codes such as Methods for Estimation of Leakages and Consequences of Releases (MELCOR) are complex tools used to simulate and analyse the progression of a severe accident from the onset of the accident up to the release from the containment. For this reason, these tools are developed in order to simulate different phenomena coupling models which can simulate simultaneously the ThermoHydraulic (TH), the physics and the chemistry. In order to evaluate the performance in the prediction of those complicated phenomena, several experimental facilities were built in Europe and all around the world. One of these facilities is the PHEBUS built by Institut de Radioprotection et de Sûrete Nucléaire (IRSN) in Cadarache. The facility reproduces the severe accident phenomena for a pressurized water reactor (PWR) on a volumetric scale of 1:5000. This paper aims to continue the assessment of the MELCOR code from version 2.1 up to version 2.2 underlying the difference in the fission product transport. The assessment of severe accident is an important step to the sustainability of the nuclear energy production in this period where the old nuclear power plants are more than the new reactors. The analyses presented in this paper focuses on models assessment with attention on the influence of B4C oxidation on the release and transport of fission products. Such phenomenon is a concern point in the nuclear industry, as was highlighted during the Fukushima Daiichi accident. Simulation of the source term is a key point to evaluate the severe accident hazard along with other safety aspects.



2004 ◽  
Vol 160 (1-4) ◽  
pp. 207-224 ◽  
Author(s):  
Young Joon Choi ◽  
Hyun Koon Kim ◽  
Won Pil Baek ◽  
Soon Heung Chang


1973 ◽  
Vol 57 (1) ◽  
pp. 68-73 ◽  
Author(s):  
Stanley Rubinsky ◽  
Nelson Smith


2016 ◽  
Vol 309 ◽  
pp. 113-121 ◽  
Author(s):  
K. Nikitin ◽  
P. Mueller ◽  
J. Martin ◽  
W. van Doesburg ◽  
D. Hiltbrand


2000 ◽  
Author(s):  
Piotr Swider ◽  
Jan Unarski ◽  
Wojciech Wach


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