Detailed, mechanistic analysis of core debris melt progression behavior in LWR's

Dosanjh, S S; Camp, W J

Title: Detailed, mechanistic analysis of core debris melt progression behavior in LWR's

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Abstract

The MELPROG code is comprised of several explicitly linked modules that analyze different aspects of an accident. Water and vapor flows in the vessel are calculated in the FLUIDS module; this module also tracks the motion of solid and molten corium that forms when vessel structures melt or fail mechanically. At the beginning of an accident, the CORE module calculates heat transfer, oxidation, clad melting, dissolution and candling in the reactor core. If the fuel rods fragment, happened at Three-Mile Island, core melt progression is analyzed in the DEBRIS module; this module also treats debris beds that can form in the lower plenum during an accident. Detailed heat transfer and structural mechanics calculations are performed in the STRUCTURES module for the vessel walls, various support plates, the core baffle, the core barrel, core support columns and various support plates, the core baffle, the core barrel, core support columns and other structures in the vessel. Three-dimensional, dynamic view factors are calculated in the RADIATION module that provides boundary conditions for the CORE, DEBRIS and STRUCTURES modules. Additional MELPROG modules are being developed to analyze fuel-coolant interactions, fission product release and the ejection of debris from the reactor vessel into the containmentmore »« less

Authors:: Dosanjh, S S; Camp, W J

Publication Date:: Mon Aug 01 00:00:00 EDT 1988

Research Org.:: Sandia National Labs., Albuquerque, NM (USA)

OSTI Identifier:: 7099124

Report Number(s):: SAND-88-0528C; CONF-881014-3
ON: DE88014521

DOE Contract Number:: AC04-76DP00789

Resource Type:: Conference

Resource Relation:: Conference: International conference on thermal reactor safety, Avignon, France, 2 Oct 1988; Other Information: Portions of this document are illegible in microfiche products

Country of Publication:: United States

Language:: English

Subject:: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; MELTDOWN; COMPUTERIZED SIMULATION; PWR TYPE REACTORS; CORIUM; HEAT TRANSFER; HYDRAULICS; M CODES; REACTOR SAFETY; RISK ASSESSMENT; ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; FLUID MECHANICS; MECHANICS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats


                    Dosanjh, S S, and Camp, W J. Detailed, mechanistic analysis of core debris melt progression behavior in LWR's.  United States: N. p., 1988. 
        Web.

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                    Dosanjh, S S, & Camp, W J. Detailed, mechanistic analysis of core debris melt progression behavior in LWR's.  United States.

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                    Dosanjh, S S, and Camp, W J. 1988.  
        "Detailed, mechanistic analysis of core debris melt progression behavior in LWR's".  United States.

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@article{osti_7099124,

  title        = {Detailed, mechanistic analysis of core debris melt progression behavior in LWR's},

  author       = {Dosanjh, S S and Camp, W J},

  abstractNote = {The MELPROG code is comprised of several explicitly linked modules that analyze different aspects of an accident. Water and vapor flows in the vessel are calculated in the FLUIDS module; this module also tracks the motion of solid and molten corium that forms when vessel structures melt or fail mechanically. At the beginning of an accident, the CORE module calculates heat transfer, oxidation, clad melting, dissolution and candling in the reactor core. If the fuel rods fragment, happened at Three-Mile Island, core melt progression is analyzed in the DEBRIS module; this module also treats debris beds that can form in the lower plenum during an accident. Detailed heat transfer and structural mechanics calculations are performed in the STRUCTURES module for the vessel walls, various support plates, the core baffle, the core barrel, core support columns and various support plates, the core baffle, the core barrel, core support columns and other structures in the vessel. Three-dimensional, dynamic view factors are calculated in the RADIATION module that provides boundary conditions for the CORE, DEBRIS and STRUCTURES modules. Additional MELPROG modules are being developed to analyze fuel-coolant interactions, fission product release and the ejection of debris from the reactor vessel into the containment building. This paper describes the MELPROG models that are operational during the late core melt progression phase of severe accidents. Brief descriptions of the FLUIDS, DEBRIS, STRUCTURES and RADIATION modules are provided in the following sections. Results from a demonstration calculation using a stand-alone version of the DEBRIS module are presented.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/7099124},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Mon Aug 01 00:00:00 EDT 1988},

  month        = {Mon Aug 01 00:00:00 EDT 1988}

}

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