Issues on containment integrity during severe accidents

Bishnoi, L.R.; Gupta, Satish Kumar

doi:10.1109/icresh.2010.5779564

Cited by 1 publication

(2 citation statements)

References 36 publications

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“…The In-vessel phenomena include the thermal-hydraulics with natural circulation, reflooding, and refilling of the core at high temperature, oxidation of the cladding, hydrogen production, relocation of the molten core into the lower plenum of the RPV, liquefaction of control rods, recriticality, and failure of the reactor vessel. The Exvessel phenomena involve steam explosion, melt dispersion, fission products transport and deposition on structures and components, direct containment heating (DCH) among others [1]; evolution and management of severe accident dependent of the RPV failure, but the uncertainty in the modeling of the phenomenon in bottom of the RPV is very high.…”

Section: Introductionmentioning

confidence: 99%

“…The objective of the work was the study of In-vessel corium retention by external vessel cooling as a series of strategies adopted in severe accident management guidelines (SAMGs) for CANDU reactor. In the work of Bishnoi and Gupta [1], the containment importance during a severe accident, in particular for Pressurized Water Reactor (PWR), is analyzed.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Simulation of the Lower Head Boiling Water Reactor Vessel in a Severe Accident

Nuñez-Carrera¹,

Camargo-Camargo²,

Espinosa-Paredes

et al. 2012

Science and Technology of Nuclear Installations

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The objective of this paper is the simulation and analysis of the BoilingWater Reactor (BWR) lower head during a severe accident. The COUPLE computer code was used in this work to model the heatup of the reactor core material that slumps in the lower head of the reactor pressure vessel. The prediction of the lower head failure is an important issue in the severe accidents field, due to the accident progression and the radiological consequences that are completely different with or without the failure of the Reactor Pressure Vessel (RPV). The release of molten material to the primary containment and the possibility of steam explosion may produce the failure of the primary containment with high radiological consequences. Then, it is important to have a detailed model in order to predict the behavior of the reactor vessel lower head in a severe accident. In this paper, a hypothetical simulation of a Loss of Coolant Accident (LOCA) with simultaneous loss of off-site power and without injection of cooling water is presented with the proposal to evaluate the temperature distribution and heatup of the lower part of the RPV. The SCDAPSIM/RELAP5 3.2 code was used to build the BWR model and conduct the numerical simulation.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%