Comparison of CORA & MELCOR core degradation simulation and the melcor oxidation model

Jun Wang; Michael L. Corradini; Wen Fu; Troy Haskin; Guanghui Su; Wenxi Tian; Suizheng Qiu; Yapei Zhang

doi:10.1115/ICONE22-30475

Comparison of CORA & MELCOR core degradation simulation and the melcor oxidation model

Jun Wang
, Michael L. Corradini
, Wen Fu
, Troy Haskin
, Guanghui Su
, Wenxi Tian
, Suizheng Qiu
, Yapei Zhang

School of Energy and Power Engineering

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

3 Scopus citations

Abstract

MELCOR is widely used and sufficiently trusted for severe accident analysis. However, the occurrence of Fukushima has increased the focus on severe accident codes and their use. A MELCOR core degradation calculation was conducted at the University of Wisconsin -Madison. The calculation results were checked by comparing with a past CORA experiment. MELCOR calculation results included the flow rate of argon and steam, the generation rate of hydrogen. Through this work, the performance of MELCOR COR package was reviewed in detail. This paper compares the hydrogen generation rates predicted by MELCOR to the CORA test data. While agreement is reasonable it could be improved. Additionally, the MELCOR zirconium oxidation model was analyzed.

Original language	English
Title of host publication	Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I and C); Fusion Engineering; Beyond Design Basis Events
Publisher	American Society of Mechanical Engineers (ASME)
ISBN (Electronic)	9780791845967
DOIs	https://doi.org/10.1115/ICONE22-30475
State	Published - 2014
Event	2014 22nd International Conference on Nuclear Engineering, ICONE 2014 - Prague, Czech Republic Duration: 7 Jul 2014 → 11 Jul 2014

Publication series

Name	International Conference on Nuclear Engineering, Proceedings, ICONE
Volume	6

Conference

Conference	2014 22nd International Conference on Nuclear Engineering, ICONE 2014
Country/Territory	Czech Republic
City	Prague
Period	7/07/14 → 11/07/14

Access to Document

10.1115/ICONE22-30475

Cite this

Wang, J., Corradini, M. L., Fu, W., Haskin, T., Su, G., Tian, W., Qiu, S., & Zhang, Y. (2014). Comparison of CORA & MELCOR core degradation simulation and the melcor oxidation model. In Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I and C); Fusion Engineering; Beyond Design Basis Events (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 6). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/ICONE22-30475

Wang, Jun ; Corradini, Michael L. ; Fu, Wen et al. / Comparison of CORA & MELCOR core degradation simulation and the melcor oxidation model. Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I and C); Fusion Engineering; Beyond Design Basis Events. American Society of Mechanical Engineers (ASME), 2014. (International Conference on Nuclear Engineering, Proceedings, ICONE).

@inproceedings{6955c38b240b4525a5579737e6a1b33f,

title = "Comparison of CORA \& MELCOR core degradation simulation and the melcor oxidation model",

abstract = "MELCOR is widely used and sufficiently trusted for severe accident analysis. However, the occurrence of Fukushima has increased the focus on severe accident codes and their use. A MELCOR core degradation calculation was conducted at the University of Wisconsin -Madison. The calculation results were checked by comparing with a past CORA experiment. MELCOR calculation results included the flow rate of argon and steam, the generation rate of hydrogen. Through this work, the performance of MELCOR COR package was reviewed in detail. This paper compares the hydrogen generation rates predicted by MELCOR to the CORA test data. While agreement is reasonable it could be improved. Additionally, the MELCOR zirconium oxidation model was analyzed.",

author = "Jun Wang and Corradini, \{Michael L.\} and Wen Fu and Troy Haskin and Guanghui Su and Wenxi Tian and Suizheng Qiu and Yapei Zhang",

note = "Publisher Copyright: Copyright {\textcopyright} 2014 by ASME.; 2014 22nd International Conference on Nuclear Engineering, ICONE 2014 ; Conference date: 07-07-2014 Through 11-07-2014",

year = "2014",

doi = "10.1115/ICONE22-30475",

language = "英语",

series = "International Conference on Nuclear Engineering, Proceedings, ICONE",

publisher = "American Society of Mechanical Engineers (ASME)",

booktitle = "Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I and C); Fusion Engineering; Beyond Design Basis Events",

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Wang, J, Corradini, ML, Fu, W, Haskin, T, Su, G , Tian, W, Qiu, S & Zhang, Y 2014, Comparison of CORA & MELCOR core degradation simulation and the melcor oxidation model. in Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I and C); Fusion Engineering; Beyond Design Basis Events. International Conference on Nuclear Engineering, Proceedings, ICONE, vol. 6, American Society of Mechanical Engineers (ASME), 2014 22nd International Conference on Nuclear Engineering, ICONE 2014, Prague, Czech Republic, 7/07/14. https://doi.org/10.1115/ICONE22-30475

Comparison of CORA & MELCOR core degradation simulation and the melcor oxidation model. / Wang, Jun; Corradini, Michael L.; Fu, Wen et al.
Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I and C); Fusion Engineering; Beyond Design Basis Events. American Society of Mechanical Engineers (ASME), 2014. (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 6).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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T1 - Comparison of CORA & MELCOR core degradation simulation and the melcor oxidation model

AU - Wang, Jun

AU - Corradini, Michael L.

AU - Fu, Wen

AU - Haskin, Troy

AU - Su, Guanghui

AU - Tian, Wenxi

AU - Qiu, Suizheng

AU - Zhang, Yapei

PY - 2014

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N2 - MELCOR is widely used and sufficiently trusted for severe accident analysis. However, the occurrence of Fukushima has increased the focus on severe accident codes and their use. A MELCOR core degradation calculation was conducted at the University of Wisconsin -Madison. The calculation results were checked by comparing with a past CORA experiment. MELCOR calculation results included the flow rate of argon and steam, the generation rate of hydrogen. Through this work, the performance of MELCOR COR package was reviewed in detail. This paper compares the hydrogen generation rates predicted by MELCOR to the CORA test data. While agreement is reasonable it could be improved. Additionally, the MELCOR zirconium oxidation model was analyzed.

AB - MELCOR is widely used and sufficiently trusted for severe accident analysis. However, the occurrence of Fukushima has increased the focus on severe accident codes and their use. A MELCOR core degradation calculation was conducted at the University of Wisconsin -Madison. The calculation results were checked by comparing with a past CORA experiment. MELCOR calculation results included the flow rate of argon and steam, the generation rate of hydrogen. Through this work, the performance of MELCOR COR package was reviewed in detail. This paper compares the hydrogen generation rates predicted by MELCOR to the CORA test data. While agreement is reasonable it could be improved. Additionally, the MELCOR zirconium oxidation model was analyzed.

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M3 - 会议稿件

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T3 - International Conference on Nuclear Engineering, Proceedings, ICONE

BT - Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I and C); Fusion Engineering; Beyond Design Basis Events

PB - American Society of Mechanical Engineers (ASME)

T2 - 2014 22nd International Conference on Nuclear Engineering, ICONE 2014

Y2 - 7 July 2014 through 11 July 2014

ER -

Wang J, Corradini ML, Fu W, Haskin T, Su G , Tian W et al. Comparison of CORA & MELCOR core degradation simulation and the melcor oxidation model. In Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I and C); Fusion Engineering; Beyond Design Basis Events. American Society of Mechanical Engineers (ASME). 2014. (International Conference on Nuclear Engineering, Proceedings, ICONE). doi: 10.1115/ICONE22-30475

Comparison of CORA & MELCOR core degradation simulation and the melcor oxidation model

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