OECD MCCI Project: Category 4 Integral Test to Validate Severe Accident Codes and Core-Concrete Interaction Test Six (CCI-6) (Rev. 2, Final Report)

OECD MCCI Project: Category 4 Integral Test to Validate Severe Accident Codes: Core-Concrete Interaction Test Six (CCI-6) Test Plan (Rev. 6)

10.2172/1177568 ◽

2010 ◽

Author(s):

M. T. Farmer ◽

D. J. Kilsdonk ◽

S. Lomperski ◽

R. W. Aeschlimann

Keyword(s):

Severe Accident ◽

Test Plan ◽

Integral Test ◽

Core Concrete ◽

Interaction Test

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OECD MCCI Project: Category 4 Integral Test to Validate Severe Accident Codes (Rev. 1, Final Report)

10.2172/1177569 ◽

2010 ◽

Cited By ~ 1

Author(s):

M. T. Farmer ◽

D. J. Kilsdonk ◽

R. W. Aeschlimann ◽

S. Lomperski

Keyword(s):

Severe Accident ◽

Final Report ◽

Integral Test

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NEUP Final Report: Multilayer Composite Fuel Cladding and Core Internals for LWR Performance Enhancement and Severe Accident Tolerance

10.2172/1572872 ◽

2019 ◽

Author(s):

Michael Philip Short ◽

Samuel McAlpine ◽

Michael Tonks ◽

Aashique Rezwan ◽

Jinsuo Zhang ◽

...

Keyword(s):

Performance Enhancement ◽

Severe Accident ◽

Final Report ◽

Multilayer Composite ◽

Fuel Cladding ◽

Composite Fuel

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Severe accident approach - final report. Evaluation of design measures for severe accident prevention and consequence mitigation.

10.2172/973483 ◽

2010 ◽

Cited By ~ 14

Author(s):

A. M. Tentner ◽

E. Parma ◽

T. Wei ◽

R. Wigeland ◽

SNL ◽

...

Keyword(s):

Accident Prevention ◽

Severe Accident ◽

Final Report ◽

Consequence Mitigation

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The Development of a Mechanistic Model of MCCI Under Severe Accidents

Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes ◽

10.1115/icone21-15088 ◽

2013 ◽

Author(s):

Wei Wei ◽

Kelin Qi ◽

Fuchang Shan ◽

Yanfang Chen ◽

Fude Guo

Keyword(s):

Nuclear Power ◽

Large Scale ◽

Mechanistic Model ◽

Severe Accident ◽

Severe Accidents ◽

Large Scale Analysis ◽

Loss Of Coolant ◽

Calculation Results ◽

Station Blackout ◽

Core Concrete

This paper describes a mechanistic model of the molten core-concrete interaction (MCCI) process under severe accidents, and selects the Daya-Bay nuclear power plant as the research object to calculate and analyze the process of the MCCI when the station blackout (SBO), or loss of coolant (LOCA) severe accident serial is happened. The calculation results of this procedure are compared with the large-scale analysis programs MELCOR to verify the reasonableness and correctness of the model. The results indicate that the model present in this paper can simulate the MCCI process correctly and reasonably under multi-serial severe accidents.

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Parametric Model for Ex-Vessel Melt Jet Breakup and Debris Bed Cooling

Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events ◽

10.1115/icone26-81465 ◽

2018 ◽

Author(s):

Kiyofumi Moriyama ◽

Hyun Sun Park ◽

Mooneon Lee ◽

Jin Ho Park

Keyword(s):

Parametric Model ◽

Light Water Reactor ◽

Severe Accident ◽

Full Model ◽

Light Water ◽

Water Reactor ◽

Jet Breakup ◽

Core Cooling ◽

Synthetic Assessment ◽

Core Concrete

The process of the ex-vessel molten core cooling in a pre-flooded reactor cavity during a severe accident of a light water reactor includes complicated phenomena such as melt jet breakup, debris bed formation and cooling and the molten core-concrete interaction. The melt coolability and its impact on the containment consequences are dependent on the interactions among those phenomena. A simplified parametric model, COOLAP-II, covering the melt jet breakup, debris bed formation and cooling was developed for the synthetic assessment of the ex-vessel melt coolability. The model was validated on the melt breakup and initial cooling by comparison with a full-model for fuel-coolant interactions, JASMINE.

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