A recent version of MELCOR for fusion safety applications

Brad J. Merrill; Paul W. Humrickhouse; Richard L. Moore

doi:10.1016/j.fusengdes.2010.04.017

A recent version of MELCOR for fusion safety applications

Brad J. Merrill, Paul W. Humrickhouse, Richard L. Moore

Research output: Contribution to journal › Article › peer-review

59 Scopus citations

Abstract

During the engineering design activity (EDA) of ITER, the MELCOR 1.8.2 code was selected as one of several codes to be used to perform ITER safety analyses. MELCOR was chosen because it has the capabilities of predicting thermal-hydraulic transients and self-consistently accounting for aerosol transport in nuclear facilities and reactor cooling systems. The Idaho National Laboratory (INL) Fusion Safety Program (FSP) organization made fusion specific modifications to the MELCOR 1.8.2 code that allows MELCOR to assess the thermal-hydraulic response of fusion reactor cooling systems and the transport of radionuclides as aerosols during accident conditions. The ITER International Organization (IO) used this version of MELCOR to perform accident analyses for ITER's "Rapport Préliminaire de Sûreté" (Report Preliminary on Safety - RPrS). Because MELCOR has undergone many improvements since version 1.8.2 was released, the INL FSP introduced these same fusion modifications into MELCOR 1.8.6, and thereby produced a version of MELCOR 1.8.6 with similar capabilities to the version of MELCOR used by the ITER IO for the ITER RPrS. We have applied this recent version of MELCOR to the analysis of a large in-vessel water leak event examined in the ITER Generic Site Safety Report (GSSR). This paper presents the results of this analysis and compares these results to those obtained from the MELCOR 1.8.2 code.

Original language	English
Pages (from-to)	1479-1483
Number of pages	5
Journal	Fusion Engineering and Design
Volume	85
Issue number	7-9
DOIs	https://doi.org/10.1016/j.fusengdes.2010.04.017
State	Published - Dec 2010
Externally published	Yes

Funding

This work was prepared under the auspices of the US Department of Energy, Office of Fusion Energy Science , under the DOE Idaho Field Office contract number DE-AC07-05ID14517 .

Funders	Funder number
Office of Fusion Energy Science
US Department of Energy
U.S. Department of Energy	DE-AC07-05ID14517

Keywords

Fusion safety
ITER
In-vessel water leak
MELCOR

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.fusengdes.2010.04.017

Cite this

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abstract = "During the engineering design activity (EDA) of ITER, the MELCOR 1.8.2 code was selected as one of several codes to be used to perform ITER safety analyses. MELCOR was chosen because it has the capabilities of predicting thermal-hydraulic transients and self-consistently accounting for aerosol transport in nuclear facilities and reactor cooling systems. The Idaho National Laboratory (INL) Fusion Safety Program (FSP) organization made fusion specific modifications to the MELCOR 1.8.2 code that allows MELCOR to assess the thermal-hydraulic response of fusion reactor cooling systems and the transport of radionuclides as aerosols during accident conditions. The ITER International Organization (IO) used this version of MELCOR to perform accident analyses for ITER's {"}Rapport Pr{\'e}liminaire de S{\^u}ret{\'e}{"} (Report Preliminary on Safety - RPrS). Because MELCOR has undergone many improvements since version 1.8.2 was released, the INL FSP introduced these same fusion modifications into MELCOR 1.8.6, and thereby produced a version of MELCOR 1.8.6 with similar capabilities to the version of MELCOR used by the ITER IO for the ITER RPrS. We have applied this recent version of MELCOR to the analysis of a large in-vessel water leak event examined in the ITER Generic Site Safety Report (GSSR). This paper presents the results of this analysis and compares these results to those obtained from the MELCOR 1.8.2 code.",

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AB - During the engineering design activity (EDA) of ITER, the MELCOR 1.8.2 code was selected as one of several codes to be used to perform ITER safety analyses. MELCOR was chosen because it has the capabilities of predicting thermal-hydraulic transients and self-consistently accounting for aerosol transport in nuclear facilities and reactor cooling systems. The Idaho National Laboratory (INL) Fusion Safety Program (FSP) organization made fusion specific modifications to the MELCOR 1.8.2 code that allows MELCOR to assess the thermal-hydraulic response of fusion reactor cooling systems and the transport of radionuclides as aerosols during accident conditions. The ITER International Organization (IO) used this version of MELCOR to perform accident analyses for ITER's "Rapport Préliminaire de Sûreté" (Report Preliminary on Safety - RPrS). Because MELCOR has undergone many improvements since version 1.8.2 was released, the INL FSP introduced these same fusion modifications into MELCOR 1.8.6, and thereby produced a version of MELCOR 1.8.6 with similar capabilities to the version of MELCOR used by the ITER IO for the ITER RPrS. We have applied this recent version of MELCOR to the analysis of a large in-vessel water leak event examined in the ITER Generic Site Safety Report (GSSR). This paper presents the results of this analysis and compares these results to those obtained from the MELCOR 1.8.2 code.

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A recent version of MELCOR for fusion safety applications

Abstract

Funding

Keywords

UN SDGs

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