Simulation of Nuclear Power Plant Containment Response During a Large-Break Loss-of-Coolant Accident

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Izvoz citacije: ABNT
KLJENAK, Ivo ;MAVKO, Borut .
Simulation of Nuclear Power Plant Containment Response During a Large-Break Loss-of-Coolant Accident. 
Strojniški vestnik - Journal of Mechanical Engineering, [S.l.], v. 46, n.6, p. 370-382, july 2017. 
ISSN 0039-2480.
Available at: <https://www.sv-jme.eu/sl/article/simulation-of-nuclear-power-plant-containment-response-during-a-large-break-loss-of-coolant-accident/>. Date accessed: 06 mar. 2021. 
doi:http://dx.doi.org/.
Kljenak, I., & Mavko, B.
(2000).
Simulation of Nuclear Power Plant Containment Response During a Large-Break Loss-of-Coolant Accident.
Strojniški vestnik - Journal of Mechanical Engineering, 46(6), 370-382.
doi:http://dx.doi.org/
@article{.,
	author = {Ivo  Kljenak and Borut  Mavko},
	title = {Simulation of Nuclear Power Plant Containment Response During a Large-Break Loss-of-Coolant Accident},
	journal = {Strojniški vestnik - Journal of Mechanical Engineering},
	volume = {46},
	number = {6},
	year = {2000},
	keywords = {nuclear power plant; containment; loss-of-coolant accident; simulations; },
	abstract = {Containment phenomena during a large-break loss-of-coolant accident in a two-loop pressurizedwater reactor nuclear power plant were simulated with the CONTAIN thermal-hydraulic computer code. Pressure and temperature responses as well as coolant and energy distributions were analyzed.},
	issn = {0039-2480},	pages = {370-382},	doi = {},
	url = {https://www.sv-jme.eu/sl/article/simulation-of-nuclear-power-plant-containment-response-during-a-large-break-loss-of-coolant-accident/}
}
Kljenak, I.,Mavko, B.
2000 July 46. Simulation of Nuclear Power Plant Containment Response During a Large-Break Loss-of-Coolant Accident. Strojniški vestnik - Journal of Mechanical Engineering. [Online] 46:6
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%A Mavko, Borut 
%D 2000
%T Simulation of Nuclear Power Plant Containment Response During a Large-Break Loss-of-Coolant Accident
%B 2000
%9 nuclear power plant; containment; loss-of-coolant accident; simulations; 
%! Simulation of Nuclear Power Plant Containment Response During a Large-Break Loss-of-Coolant Accident
%K nuclear power plant; containment; loss-of-coolant accident; simulations; 
%X Containment phenomena during a large-break loss-of-coolant accident in a two-loop pressurizedwater reactor nuclear power plant were simulated with the CONTAIN thermal-hydraulic computer code. Pressure and temperature responses as well as coolant and energy distributions were analyzed.
%U https://www.sv-jme.eu/sl/article/simulation-of-nuclear-power-plant-containment-response-during-a-large-break-loss-of-coolant-accident/
%0 Journal Article
%R 
%& 370
%P 13
%J Strojniški vestnik - Journal of Mechanical Engineering
%V 46
%N 6
%@ 0039-2480
%8 2017-07-07
%7 2017-07-07
Kljenak, Ivo, & Borut  Mavko.
"Simulation of Nuclear Power Plant Containment Response During a Large-Break Loss-of-Coolant Accident." Strojniški vestnik - Journal of Mechanical Engineering [Online], 46.6 (2000): 370-382. Web.  06 Mar. 2021
TY  - JOUR
AU  - Kljenak, Ivo 
AU  - Mavko, Borut 
PY  - 2000
TI  - Simulation of Nuclear Power Plant Containment Response During a Large-Break Loss-of-Coolant Accident
JF  - Strojniški vestnik - Journal of Mechanical Engineering
DO  - 
KW  - nuclear power plant; containment; loss-of-coolant accident; simulations; 
N2  - Containment phenomena during a large-break loss-of-coolant accident in a two-loop pressurizedwater reactor nuclear power plant were simulated with the CONTAIN thermal-hydraulic computer code. Pressure and temperature responses as well as coolant and energy distributions were analyzed.
UR  - https://www.sv-jme.eu/sl/article/simulation-of-nuclear-power-plant-containment-response-during-a-large-break-loss-of-coolant-accident/
@article{{}{.},
	author = {Kljenak, I., Mavko, B.},
	title = {Simulation of Nuclear Power Plant Containment Response During a Large-Break Loss-of-Coolant Accident},
	journal = {Strojniški vestnik - Journal of Mechanical Engineering},
	volume = {46},
	number = {6},
	year = {2000},
	doi = {},
	url = {https://www.sv-jme.eu/sl/article/simulation-of-nuclear-power-plant-containment-response-during-a-large-break-loss-of-coolant-accident/}
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TY  - JOUR
AU  - Kljenak, Ivo 
AU  - Mavko, Borut 
PY  - 2017/07/07
TI  - Simulation of Nuclear Power Plant Containment Response During a Large-Break Loss-of-Coolant Accident
JF  - Strojniški vestnik - Journal of Mechanical Engineering; Vol 46, No 6 (2000): Strojniški vestnik - Journal of Mechanical Engineering
DO  - 
KW  - nuclear power plant, containment, loss-of-coolant accident, simulations, 
N2  - Containment phenomena during a large-break loss-of-coolant accident in a two-loop pressurizedwater reactor nuclear power plant were simulated with the CONTAIN thermal-hydraulic computer code. Pressure and temperature responses as well as coolant and energy distributions were analyzed.
UR  - https://www.sv-jme.eu/sl/article/simulation-of-nuclear-power-plant-containment-response-during-a-large-break-loss-of-coolant-accident/
Kljenak, Ivo, AND Mavko, Borut.
"Simulation of Nuclear Power Plant Containment Response During a Large-Break Loss-of-Coolant Accident" Strojniški vestnik - Journal of Mechanical Engineering [Online], Volume 46 Number 6 (07 July 2017)

Avtorji

Inštitucije

  • Jože Stefan Institute, Reactor Engineering Devision, Slovenia
  • Jože Stefan Institute, Reactor Engineering Devision, Slovenia

Informacije o papirju

Strojniški vestnik - Journal of Mechanical Engineering 46(2000)6, 370-382

Containment phenomena during a large-break loss-of-coolant accident in a two-loop pressurizedwater reactor nuclear power plant were simulated with the CONTAIN thermal-hydraulic computer code. Pressure and temperature responses as well as coolant and energy distributions were analyzed.

nuclear power plant; containment; loss-of-coolant accident; simulations;