Analysis of Ex-Vessel Steam Explosion Pressure Loads

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Izvoz citacije: ABNT
URŠIČ, Mitja ;LESKOVAR, Matjaž .
Analysis of Ex-Vessel Steam Explosion Pressure Loads. 
Strojniški vestnik - Journal of Mechanical Engineering, [S.l.], v. 56, n.6, p. 368-376, october 2017. 
ISSN 0039-2480.
Available at: <https://www.sv-jme.eu/sl/article/analysis-of-ex-vessel-steam-explosion-pressure-loads/>. Date accessed: 11 apr. 2021. 
doi:http://dx.doi.org/.
Uršič, M., & Leskovar, M.
(2010).
Analysis of Ex-Vessel Steam Explosion Pressure Loads.
Strojniški vestnik - Journal of Mechanical Engineering, 56(6), 368-376.
doi:http://dx.doi.org/
@article{.,
	author = {Mitja  Uršič and Matjaž  Leskovar},
	title = {Analysis of Ex-Vessel Steam Explosion Pressure Loads},
	journal = {Strojniški vestnik - Journal of Mechanical Engineering},
	volume = {56},
	number = {6},
	year = {2010},
	keywords = {fuel-coolant interaction; steam explotion; severe accident; simulation; },
	abstract = {An ex-vessel steam explosion in a nuclear power plant may develop when the reactor vessel fails and the molten core interacts with the coolant water in the reactor vessel. At the fuel coolant interaction a part of the corium energy is intensively transferred to water in a very short time scale. The water vaporizes at high pressure and expands, inducing potentially severe dynamic loadings on surrounding systems, structures and components that may lead to an early release of radioactive material into the environment. To get a better understanding of the ex-vessel steam explosion phenomenon, various scenarios analyses for a typical pressurized water reactor cavity were made. A detailed analysis was performed varying the melt release location, the cavity water temperature, the primary system over-pressure at vessel failure and the triggering time for explosion calculations. The main purpose of the analysis was to determine the most challenging ex-vessel steam explosion cases and to estimate the expected pressure loadings on the cavity walls. The performed analysis shows that for some ex-vessel steam explosion scenarios significantly higher pressure loads are predicted than were obtained in the OECD programme SERENA. The detailed analysis of the most challenging central melt pour scenario revealed that the calculated high pressure loads are also a consequence of the axial symmetric geometry of the cavity model and the probably over-predicted melt droplets amount involved in the steam explosion.},
	issn = {0039-2480},	pages = {368-376},	doi = {},
	url = {https://www.sv-jme.eu/sl/article/analysis-of-ex-vessel-steam-explosion-pressure-loads/}
}
Uršič, M.,Leskovar, M.
2010 October 56. Analysis of Ex-Vessel Steam Explosion Pressure Loads. Strojniški vestnik - Journal of Mechanical Engineering. [Online] 56:6
%A Uršič, Mitja 
%A Leskovar, Matjaž 
%D 2010
%T Analysis of Ex-Vessel Steam Explosion Pressure Loads
%B 2010
%9 fuel-coolant interaction; steam explotion; severe accident; simulation; 
%! Analysis of Ex-Vessel Steam Explosion Pressure Loads
%K fuel-coolant interaction; steam explotion; severe accident; simulation; 
%X An ex-vessel steam explosion in a nuclear power plant may develop when the reactor vessel fails and the molten core interacts with the coolant water in the reactor vessel. At the fuel coolant interaction a part of the corium energy is intensively transferred to water in a very short time scale. The water vaporizes at high pressure and expands, inducing potentially severe dynamic loadings on surrounding systems, structures and components that may lead to an early release of radioactive material into the environment. To get a better understanding of the ex-vessel steam explosion phenomenon, various scenarios analyses for a typical pressurized water reactor cavity were made. A detailed analysis was performed varying the melt release location, the cavity water temperature, the primary system over-pressure at vessel failure and the triggering time for explosion calculations. The main purpose of the analysis was to determine the most challenging ex-vessel steam explosion cases and to estimate the expected pressure loadings on the cavity walls. The performed analysis shows that for some ex-vessel steam explosion scenarios significantly higher pressure loads are predicted than were obtained in the OECD programme SERENA. The detailed analysis of the most challenging central melt pour scenario revealed that the calculated high pressure loads are also a consequence of the axial symmetric geometry of the cavity model and the probably over-predicted melt droplets amount involved in the steam explosion.
%U https://www.sv-jme.eu/sl/article/analysis-of-ex-vessel-steam-explosion-pressure-loads/
%0 Journal Article
%R 
%& 368
%P 9
%J Strojniški vestnik - Journal of Mechanical Engineering
%V 56
%N 6
%@ 0039-2480
%8 2017-10-24
%7 2017-10-24
Uršič, Mitja, & Matjaž  Leskovar.
"Analysis of Ex-Vessel Steam Explosion Pressure Loads." Strojniški vestnik - Journal of Mechanical Engineering [Online], 56.6 (2010): 368-376. Web.  11 Apr. 2021
TY  - JOUR
AU  - Uršič, Mitja 
AU  - Leskovar, Matjaž 
PY  - 2010
TI  - Analysis of Ex-Vessel Steam Explosion Pressure Loads
JF  - Strojniški vestnik - Journal of Mechanical Engineering
DO  - 
KW  - fuel-coolant interaction; steam explotion; severe accident; simulation; 
N2  - An ex-vessel steam explosion in a nuclear power plant may develop when the reactor vessel fails and the molten core interacts with the coolant water in the reactor vessel. At the fuel coolant interaction a part of the corium energy is intensively transferred to water in a very short time scale. The water vaporizes at high pressure and expands, inducing potentially severe dynamic loadings on surrounding systems, structures and components that may lead to an early release of radioactive material into the environment. To get a better understanding of the ex-vessel steam explosion phenomenon, various scenarios analyses for a typical pressurized water reactor cavity were made. A detailed analysis was performed varying the melt release location, the cavity water temperature, the primary system over-pressure at vessel failure and the triggering time for explosion calculations. The main purpose of the analysis was to determine the most challenging ex-vessel steam explosion cases and to estimate the expected pressure loadings on the cavity walls. The performed analysis shows that for some ex-vessel steam explosion scenarios significantly higher pressure loads are predicted than were obtained in the OECD programme SERENA. The detailed analysis of the most challenging central melt pour scenario revealed that the calculated high pressure loads are also a consequence of the axial symmetric geometry of the cavity model and the probably over-predicted melt droplets amount involved in the steam explosion.
UR  - https://www.sv-jme.eu/sl/article/analysis-of-ex-vessel-steam-explosion-pressure-loads/
@article{{}{.},
	author = {Uršič, M., Leskovar, M.},
	title = {Analysis of Ex-Vessel Steam Explosion Pressure Loads},
	journal = {Strojniški vestnik - Journal of Mechanical Engineering},
	volume = {56},
	number = {6},
	year = {2010},
	doi = {},
	url = {https://www.sv-jme.eu/sl/article/analysis-of-ex-vessel-steam-explosion-pressure-loads/}
}
TY  - JOUR
AU  - Uršič, Mitja 
AU  - Leskovar, Matjaž 
PY  - 2017/10/24
TI  - Analysis of Ex-Vessel Steam Explosion Pressure Loads
JF  - Strojniški vestnik - Journal of Mechanical Engineering; Vol 56, No 6 (2010): Strojniški vestnik - Journal of Mechanical Engineering
DO  - 
KW  - fuel-coolant interaction, steam explotion, severe accident, simulation, 
N2  - An ex-vessel steam explosion in a nuclear power plant may develop when the reactor vessel fails and the molten core interacts with the coolant water in the reactor vessel. At the fuel coolant interaction a part of the corium energy is intensively transferred to water in a very short time scale. The water vaporizes at high pressure and expands, inducing potentially severe dynamic loadings on surrounding systems, structures and components that may lead to an early release of radioactive material into the environment. To get a better understanding of the ex-vessel steam explosion phenomenon, various scenarios analyses for a typical pressurized water reactor cavity were made. A detailed analysis was performed varying the melt release location, the cavity water temperature, the primary system over-pressure at vessel failure and the triggering time for explosion calculations. The main purpose of the analysis was to determine the most challenging ex-vessel steam explosion cases and to estimate the expected pressure loadings on the cavity walls. The performed analysis shows that for some ex-vessel steam explosion scenarios significantly higher pressure loads are predicted than were obtained in the OECD programme SERENA. The detailed analysis of the most challenging central melt pour scenario revealed that the calculated high pressure loads are also a consequence of the axial symmetric geometry of the cavity model and the probably over-predicted melt droplets amount involved in the steam explosion.
UR  - https://www.sv-jme.eu/sl/article/analysis-of-ex-vessel-steam-explosion-pressure-loads/
Uršič, Mitja, AND Leskovar, Matjaž.
"Analysis of Ex-Vessel Steam Explosion Pressure Loads" Strojniški vestnik - Journal of Mechanical Engineering [Online], Volume 56 Number 6 (24 October 2017)

Avtorji

Inštitucije

  • Jožef Stefan Institute, Slovenia
  • Jožef Stefan Institute, Slovenia

Informacije o papirju

Strojniški vestnik - Journal of Mechanical Engineering 56(2010)6, 368-376

An ex-vessel steam explosion in a nuclear power plant may develop when the reactor vessel fails and the molten core interacts with the coolant water in the reactor vessel. At the fuel coolant interaction a part of the corium energy is intensively transferred to water in a very short time scale. The water vaporizes at high pressure and expands, inducing potentially severe dynamic loadings on surrounding systems, structures and components that may lead to an early release of radioactive material into the environment. To get a better understanding of the ex-vessel steam explosion phenomenon, various scenarios analyses for a typical pressurized water reactor cavity were made. A detailed analysis was performed varying the melt release location, the cavity water temperature, the primary system over-pressure at vessel failure and the triggering time for explosion calculations. The main purpose of the analysis was to determine the most challenging ex-vessel steam explosion cases and to estimate the expected pressure loadings on the cavity walls. The performed analysis shows that for some ex-vessel steam explosion scenarios significantly higher pressure loads are predicted than were obtained in the OECD programme SERENA. The detailed analysis of the most challenging central melt pour scenario revealed that the calculated high pressure loads are also a consequence of the axial symmetric geometry of the cavity model and the probably over-predicted melt droplets amount involved in the steam explosion.

fuel-coolant interaction; steam explotion; severe accident; simulation;