The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krško NPP in the Case of the SB LOCA

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BAŠIĆ, Ivica ;CRNJAC, Peter .
The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krško NPP in the Case of the SB LOCA. 
Strojniški vestnik - Journal of Mechanical Engineering, [S.l.], v. 52, n.6, p. 404-418, august 2017. 
ISSN 0039-2480.
Available at: <https://www.sv-jme.eu/sl/article/the-estimated-influence-of-the-input-parameters-in-the-analysis-of-the-pts-in-the-core-of-the-pwr-kr%c2%9ako-npp-in-the-case-of-the-sb-loca/>. Date accessed: 11 may. 2021. 
doi:http://dx.doi.org/.
Bašić, I., & Crnjac, P.
(2006).
The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krško NPP in the Case of the SB LOCA.
Strojniški vestnik - Journal of Mechanical Engineering, 52(6), 404-418.
doi:http://dx.doi.org/
@article{.,
	author = {Ivica  Bašić and Peter  Crnjac},
	title = {The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krško NPP in the Case of the SB LOCA},
	journal = {Strojniški vestnik - Journal of Mechanical Engineering},
	volume = {52},
	number = {6},
	year = {2006},
	keywords = {nuclear reactors; pressure vessels; pressurized thermal chock; SB LOCA accident; },
	abstract = {This paper focuses on the deterministic method of limiting cases of the Krško Nuclear Power Plant (NPP) reactor pressure-vessel cooling by mediating the emergency core-cooling system (ECCS) during a small-break loss-of-coolant accident (SB LOCA). The SB LOCA accident with the equivalent diameter break of 50.8 mm in the cold leg and the RELAP5/MOD3.3 computer code were selected for the basic calculation. In further study, by modifying the ECCS’s parameters for the same break, three accidents of the SB LOCA were simulated. The purpose of our study was to estimate the potential risk of the extreme conservative input parameters for the pressurized thermal shock (PTS) in the reactor’s pressure vessel.},
	issn = {0039-2480},	pages = {404-418},	doi = {},
	url = {https://www.sv-jme.eu/sl/article/the-estimated-influence-of-the-input-parameters-in-the-analysis-of-the-pts-in-the-core-of-the-pwr-kr%c2%9ako-npp-in-the-case-of-the-sb-loca/}
}
Bašić, I.,Crnjac, P.
2006 August 52. The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krško NPP in the Case of the SB LOCA. Strojniški vestnik - Journal of Mechanical Engineering. [Online] 52:6
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%A Crnjac, Peter 
%D 2006
%T The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krško NPP in the Case of the SB LOCA
%B 2006
%9 nuclear reactors; pressure vessels; pressurized thermal chock; SB LOCA accident; 
%! The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krško NPP in the Case of the SB LOCA
%K nuclear reactors; pressure vessels; pressurized thermal chock; SB LOCA accident; 
%X This paper focuses on the deterministic method of limiting cases of the Krško Nuclear Power Plant (NPP) reactor pressure-vessel cooling by mediating the emergency core-cooling system (ECCS) during a small-break loss-of-coolant accident (SB LOCA). The SB LOCA accident with the equivalent diameter break of 50.8 mm in the cold leg and the RELAP5/MOD3.3 computer code were selected for the basic calculation. In further study, by modifying the ECCS’s parameters for the same break, three accidents of the SB LOCA were simulated. The purpose of our study was to estimate the potential risk of the extreme conservative input parameters for the pressurized thermal shock (PTS) in the reactor’s pressure vessel.
%U https://www.sv-jme.eu/sl/article/the-estimated-influence-of-the-input-parameters-in-the-analysis-of-the-pts-in-the-core-of-the-pwr-kr%c2%9ako-npp-in-the-case-of-the-sb-loca/
%0 Journal Article
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%& 404
%P 15
%J Strojniški vestnik - Journal of Mechanical Engineering
%V 52
%N 6
%@ 0039-2480
%8 2017-08-18
%7 2017-08-18
Bašić, Ivica, & Peter  Crnjac.
"The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krško NPP in the Case of the SB LOCA." Strojniški vestnik - Journal of Mechanical Engineering [Online], 52.6 (2006): 404-418. Web.  11 May. 2021
TY  - JOUR
AU  - Bašić, Ivica 
AU  - Crnjac, Peter 
PY  - 2006
TI  - The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krško NPP in the Case of the SB LOCA
JF  - Strojniški vestnik - Journal of Mechanical Engineering
DO  - 
KW  - nuclear reactors; pressure vessels; pressurized thermal chock; SB LOCA accident; 
N2  - This paper focuses on the deterministic method of limiting cases of the Krško Nuclear Power Plant (NPP) reactor pressure-vessel cooling by mediating the emergency core-cooling system (ECCS) during a small-break loss-of-coolant accident (SB LOCA). The SB LOCA accident with the equivalent diameter break of 50.8 mm in the cold leg and the RELAP5/MOD3.3 computer code were selected for the basic calculation. In further study, by modifying the ECCS’s parameters for the same break, three accidents of the SB LOCA were simulated. The purpose of our study was to estimate the potential risk of the extreme conservative input parameters for the pressurized thermal shock (PTS) in the reactor’s pressure vessel.
UR  - https://www.sv-jme.eu/sl/article/the-estimated-influence-of-the-input-parameters-in-the-analysis-of-the-pts-in-the-core-of-the-pwr-kr%c2%9ako-npp-in-the-case-of-the-sb-loca/
@article{{}{.},
	author = {Bašić, I., Crnjac, P.},
	title = {The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krško NPP in the Case of the SB LOCA},
	journal = {Strojniški vestnik - Journal of Mechanical Engineering},
	volume = {52},
	number = {6},
	year = {2006},
	doi = {},
	url = {https://www.sv-jme.eu/sl/article/the-estimated-influence-of-the-input-parameters-in-the-analysis-of-the-pts-in-the-core-of-the-pwr-kr%c2%9ako-npp-in-the-case-of-the-sb-loca/}
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TY  - JOUR
AU  - Bašić, Ivica 
AU  - Crnjac, Peter 
PY  - 2017/08/18
TI  - The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krško NPP in the Case of the SB LOCA
JF  - Strojniški vestnik - Journal of Mechanical Engineering; Vol 52, No 6 (2006): Strojniški vestnik - Journal of Mechanical Engineering
DO  - 
KW  - nuclear reactors, pressure vessels, pressurized thermal chock, SB LOCA accident, 
N2  - This paper focuses on the deterministic method of limiting cases of the Krško Nuclear Power Plant (NPP) reactor pressure-vessel cooling by mediating the emergency core-cooling system (ECCS) during a small-break loss-of-coolant accident (SB LOCA). The SB LOCA accident with the equivalent diameter break of 50.8 mm in the cold leg and the RELAP5/MOD3.3 computer code were selected for the basic calculation. In further study, by modifying the ECCS’s parameters for the same break, three accidents of the SB LOCA were simulated. The purpose of our study was to estimate the potential risk of the extreme conservative input parameters for the pressurized thermal shock (PTS) in the reactor’s pressure vessel.
UR  - https://www.sv-jme.eu/sl/article/the-estimated-influence-of-the-input-parameters-in-the-analysis-of-the-pts-in-the-core-of-the-pwr-kr%c2%9ako-npp-in-the-case-of-the-sb-loca/
Bašić, Ivica, AND Crnjac, Peter.
"The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krško NPP in the Case of the SB LOCA" Strojniški vestnik - Journal of Mechanical Engineering [Online], Volume 52 Number 6 (18 August 2017)

Avtorji

Inštitucije

  • Nuclear Power Plant Krško, Slovenia
  • II. Gimnazija Maribor, Slovenia

Informacije o papirju

Strojniški vestnik - Journal of Mechanical Engineering 52(2006)6, 404-418

This paper focuses on the deterministic method of limiting cases of the Krško Nuclear Power Plant (NPP) reactor pressure-vessel cooling by mediating the emergency core-cooling system (ECCS) during a small-break loss-of-coolant accident (SB LOCA). The SB LOCA accident with the equivalent diameter break of 50.8 mm in the cold leg and the RELAP5/MOD3.3 computer code were selected for the basic calculation. In further study, by modifying the ECCS’s parameters for the same break, three accidents of the SB LOCA were simulated. The purpose of our study was to estimate the potential risk of the extreme conservative input parameters for the pressurized thermal shock (PTS) in the reactor’s pressure vessel.

nuclear reactors; pressure vessels; pressurized thermal chock; SB LOCA accident;