Zobrazeno 1 - 7
of 7
pro vyhledávání: '"N. P. Kolev"'
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2010 (2010)
The paper presents validation results for multichannel vessel thermal-hydraulic models in CATHARE used in coupled 3D neutronic/thermal hydraulic calculations. The mixing is modeled with cross flows governed by local pressure drops. The test cases are
Externí odkaz:
https://doaj.org/article/279b36f3303040b8a4f74115933fd862
Publikováno v:
Алматы технологиялық университетінің хабаршысы, Vol 0, Iss 3, Pp 130-137 (2022)
In most cases, the color of meat products is the factor influencing consumer choice. It’s formation and preservation is the highest priority. Sodium nitrite is used for fixation of the pleasant pink-red color, but also has a negative image from the
Externí odkaz:
https://doaj.org/article/176150a276b64c70a4c1bf62774a3469
Publikováno v:
THERMOPHYSICAL BASIS OF ENERGY TECHNOLOGIES (TBET 2020).
The paper presents validation results for multi-1D thermal-hydraulic models with RELAP/SCDAPSIM mod3.5 used for pseudo-3D reactor vessel simulation. The main objective is to test the capabilities and limitations of such calculation models to represen
Publikováno v:
Kerntechnik. 83:389-395
A hypothetical main steam line break transient in a VVER-1000 core with multiple equipment faults was simulated with the coupled COBAYA4/CTF and COBAYA3/FLICA4 nodal core models. The objective was to test recent versions of the models developed in th
Autor:
L. Vyskocil, Victor Sanchez, A. Sabater, S. Mitkov, Javier Jimenez, N. P. Kolev, D. Cuervo, S. Sánchez-Cervera, I. G. Spasov, N. García-Herranz
Publikováno v:
Nuclear Engineering and Design, ISSN 0029-5493, 2017-09, Vol. 321
Archivo Digital UPM
Universidad Politécnica de Madrid
Archivo Digital UPM
Universidad Politécnica de Madrid
This paper summarizes the nodal level results from the VVER MSLB core simulation in the NURESAFE EU project. The main objective is to implement and verify new developments in the models and couplings of 3D core simulators for cores with hexagonal fue
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::fd54dbcb24e71ca26a390ecc5adf8db9
http://oa.upm.es/49805/
http://oa.upm.es/49805/
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2010 (2010)
The paper presents validation results for multichannel vessel thermal-hydraulic models in CATHARE used in coupled 3D neutronic/thermal hydraulic calculations. The mixing is modeled with cross flows governed by local pressure drops. The test cases are
Autor:
I. A. Kurtev, Zh. I. Kostov, V. D. Filev, A. I. Lazarov, E. Kh. Manov, N. P. Kolev, D. S. Rusev
Publikováno v:
Measurement Techniques. 19:512-515