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/article/simulation-of-nuclear-power-plant-containment-response-during-a-large-break-loss-of-coolant-accident/>. Date accessed: 04 oct. 2024. 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/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
%A Kljenak, Ivo %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/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. 04 Oct. 2024
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/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/article/simulation-of-nuclear-power-plant-containment-response-during-a-large-break-loss-of-coolant-accident/} }
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/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)
Strojniški vestnik - Journal of Mechanical Engineering 46(2000)6, 370-382
© The Authors, CC-BY 4.0 Int. Change in copyright policy from 2022, Jan 1st.
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.