Simulation of the Phebus FPT1 Severe Accident Experiment with the MELCOR Computer Code

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LESKOVAR, Matjaž ;MAVKO, Borut .
Simulation of the Phebus FPT1 Severe Accident Experiment with the MELCOR Computer Code. 
Strojniški vestnik - Journal of Mechanical Engineering, [S.l.], v. 52, n.3, p. 142-160, august 2017. 
ISSN 0039-2480.
Available at: <https://www.sv-jme.eu/article/simulation-of-the-phebus-fpt1-severe-accident-experiment-with-the-melcor-computer-code/>. Date accessed: 21 sep. 2021. 
doi:http://dx.doi.org/.
Leskovar, M., & Mavko, B.
(2006).
Simulation of the Phebus FPT1 Severe Accident Experiment with the MELCOR Computer Code.
Strojniški vestnik - Journal of Mechanical Engineering, 52(3), 142-160.
doi:http://dx.doi.org/
@article{.,
	author = {Matjaž  Leskovar and Borut  Mavko},
	title = {Simulation of the Phebus FPT1 Severe Accident Experiment with the MELCOR Computer Code},
	journal = {Strojniški vestnik - Journal of Mechanical Engineering},
	volume = {52},
	number = {3},
	year = {2006},
	keywords = {reactor accident; modelling; simulation; PHEBUS; MELCOR; },
	abstract = {As part of the OECD International Standard Problem No. 46, the thermal-hydraulic, fuel-degradation and aerosol phenomena, which occurred in the bundle and circuit of the Phebus facility during the degradation phase of the Phebus FPT1 experiment, were simulated with two versions of MELCOR 1.8.5 (QZ and RE). The input model was developed by strictly following the recommendations on noding and the use of the default parameters provided in the ISP-46 Specification Report. Special attention was given to the modelling of the specifics of the Phebus facility. A comparison of the simulation results and the experimental measurements showed good agreement for the thermal-hydraulic variables and satisfactory agreement for the total releases for most radio-nuclides, whereas the radio-nuclide depositions in the steam generator were overestimated. The timing of the key events was relatively well predicted. The differences between the simulation results of both MELCOR versions were negligible for the thermal-hydraulic variables, small for the radio-nuclide releases and the timing of the key events, but significant for the radio-nuclide depositions and the bundle degradation. In general, the results of the newer MELCOR 1.8.5 version RE show better agreement with the experimental measurements.},
	issn = {0039-2480},	pages = {142-160},	doi = {},
	url = {https://www.sv-jme.eu/article/simulation-of-the-phebus-fpt1-severe-accident-experiment-with-the-melcor-computer-code/}
}
Leskovar, M.,Mavko, B.
2006 August 52. Simulation of the Phebus FPT1 Severe Accident Experiment with the MELCOR Computer Code. Strojniški vestnik - Journal of Mechanical Engineering. [Online] 52:3
%A Leskovar, Matjaž 
%A Mavko, Borut 
%D 2006
%T Simulation of the Phebus FPT1 Severe Accident Experiment with the MELCOR Computer Code
%B 2006
%9 reactor accident; modelling; simulation; PHEBUS; MELCOR; 
%! Simulation of the Phebus FPT1 Severe Accident Experiment with the MELCOR Computer Code
%K reactor accident; modelling; simulation; PHEBUS; MELCOR; 
%X As part of the OECD International Standard Problem No. 46, the thermal-hydraulic, fuel-degradation and aerosol phenomena, which occurred in the bundle and circuit of the Phebus facility during the degradation phase of the Phebus FPT1 experiment, were simulated with two versions of MELCOR 1.8.5 (QZ and RE). The input model was developed by strictly following the recommendations on noding and the use of the default parameters provided in the ISP-46 Specification Report. Special attention was given to the modelling of the specifics of the Phebus facility. A comparison of the simulation results and the experimental measurements showed good agreement for the thermal-hydraulic variables and satisfactory agreement for the total releases for most radio-nuclides, whereas the radio-nuclide depositions in the steam generator were overestimated. The timing of the key events was relatively well predicted. The differences between the simulation results of both MELCOR versions were negligible for the thermal-hydraulic variables, small for the radio-nuclide releases and the timing of the key events, but significant for the radio-nuclide depositions and the bundle degradation. In general, the results of the newer MELCOR 1.8.5 version RE show better agreement with the experimental measurements.
%U https://www.sv-jme.eu/article/simulation-of-the-phebus-fpt1-severe-accident-experiment-with-the-melcor-computer-code/
%0 Journal Article
%R 
%& 142
%P 19
%J Strojniški vestnik - Journal of Mechanical Engineering
%V 52
%N 3
%@ 0039-2480
%8 2017-08-18
%7 2017-08-18
Leskovar, Matjaž, & Borut  Mavko.
"Simulation of the Phebus FPT1 Severe Accident Experiment with the MELCOR Computer Code." Strojniški vestnik - Journal of Mechanical Engineering [Online], 52.3 (2006): 142-160. Web.  21 Sep. 2021
TY  - JOUR
AU  - Leskovar, Matjaž 
AU  - Mavko, Borut 
PY  - 2006
TI  - Simulation of the Phebus FPT1 Severe Accident Experiment with the MELCOR Computer Code
JF  - Strojniški vestnik - Journal of Mechanical Engineering
DO  - 
KW  - reactor accident; modelling; simulation; PHEBUS; MELCOR; 
N2  - As part of the OECD International Standard Problem No. 46, the thermal-hydraulic, fuel-degradation and aerosol phenomena, which occurred in the bundle and circuit of the Phebus facility during the degradation phase of the Phebus FPT1 experiment, were simulated with two versions of MELCOR 1.8.5 (QZ and RE). The input model was developed by strictly following the recommendations on noding and the use of the default parameters provided in the ISP-46 Specification Report. Special attention was given to the modelling of the specifics of the Phebus facility. A comparison of the simulation results and the experimental measurements showed good agreement for the thermal-hydraulic variables and satisfactory agreement for the total releases for most radio-nuclides, whereas the radio-nuclide depositions in the steam generator were overestimated. The timing of the key events was relatively well predicted. The differences between the simulation results of both MELCOR versions were negligible for the thermal-hydraulic variables, small for the radio-nuclide releases and the timing of the key events, but significant for the radio-nuclide depositions and the bundle degradation. In general, the results of the newer MELCOR 1.8.5 version RE show better agreement with the experimental measurements.
UR  - https://www.sv-jme.eu/article/simulation-of-the-phebus-fpt1-severe-accident-experiment-with-the-melcor-computer-code/
@article{{}{.},
	author = {Leskovar, M., Mavko, B.},
	title = {Simulation of the Phebus FPT1 Severe Accident Experiment with the MELCOR Computer Code},
	journal = {Strojniški vestnik - Journal of Mechanical Engineering},
	volume = {52},
	number = {3},
	year = {2006},
	doi = {},
	url = {https://www.sv-jme.eu/article/simulation-of-the-phebus-fpt1-severe-accident-experiment-with-the-melcor-computer-code/}
}
TY  - JOUR
AU  - Leskovar, Matjaž 
AU  - Mavko, Borut 
PY  - 2017/08/18
TI  - Simulation of the Phebus FPT1 Severe Accident Experiment with the MELCOR Computer Code
JF  - Strojniški vestnik - Journal of Mechanical Engineering; Vol 52, No 3 (2006): Strojniški vestnik - Journal of Mechanical Engineering
DO  - 
KW  - reactor accident, modelling, simulation, PHEBUS, MELCOR, 
N2  - As part of the OECD International Standard Problem No. 46, the thermal-hydraulic, fuel-degradation and aerosol phenomena, which occurred in the bundle and circuit of the Phebus facility during the degradation phase of the Phebus FPT1 experiment, were simulated with two versions of MELCOR 1.8.5 (QZ and RE). The input model was developed by strictly following the recommendations on noding and the use of the default parameters provided in the ISP-46 Specification Report. Special attention was given to the modelling of the specifics of the Phebus facility. A comparison of the simulation results and the experimental measurements showed good agreement for the thermal-hydraulic variables and satisfactory agreement for the total releases for most radio-nuclides, whereas the radio-nuclide depositions in the steam generator were overestimated. The timing of the key events was relatively well predicted. The differences between the simulation results of both MELCOR versions were negligible for the thermal-hydraulic variables, small for the radio-nuclide releases and the timing of the key events, but significant for the radio-nuclide depositions and the bundle degradation. In general, the results of the newer MELCOR 1.8.5 version RE show better agreement with the experimental measurements.
UR  - https://www.sv-jme.eu/article/simulation-of-the-phebus-fpt1-severe-accident-experiment-with-the-melcor-computer-code/
Leskovar, Matjaž, AND Mavko, Borut.
"Simulation of the Phebus FPT1 Severe Accident Experiment with the MELCOR Computer Code" Strojniški vestnik - Journal of Mechanical Engineering [Online], Volume 52 Number 3 (18 August 2017)

Authors

Affiliations

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

Paper's information

Strojniški vestnik - Journal of Mechanical Engineering 52(2006)3, 142-160

As part of the OECD International Standard Problem No. 46, the thermal-hydraulic, fuel-degradation and aerosol phenomena, which occurred in the bundle and circuit of the Phebus facility during the degradation phase of the Phebus FPT1 experiment, were simulated with two versions of MELCOR 1.8.5 (QZ and RE). The input model was developed by strictly following the recommendations on noding and the use of the default parameters provided in the ISP-46 Specification Report. Special attention was given to the modelling of the specifics of the Phebus facility. A comparison of the simulation results and the experimental measurements showed good agreement for the thermal-hydraulic variables and satisfactory agreement for the total releases for most radio-nuclides, whereas the radio-nuclide depositions in the steam generator were overestimated. The timing of the key events was relatively well predicted. The differences between the simulation results of both MELCOR versions were negligible for the thermal-hydraulic variables, small for the radio-nuclide releases and the timing of the key events, but significant for the radio-nuclide depositions and the bundle degradation. In general, the results of the newer MELCOR 1.8.5 version RE show better agreement with the experimental measurements.

reactor accident; modelling; simulation; PHEBUS; MELCOR;