Light Water Reactor Safety

Sehgal, Bal Raj

doi:10.1016/b978-0-12-388446-6.00001-0

Cited by 62 publications

(32 citation statements)

References 5 publications

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“…This is the first accident that let people realize the speed of a core melt accident and the effectiveness of the implemented safety systems. The accident began with of the loss of feed water to the steam generators which caused drying out of the steam generator's secondary side for approximately 10-15 min (Sehgal, 2012). The in-vessel pressure kept increasing, while the turbine stopped running and the reactor shut down.…”

Section: Tmi Accidentmentioning

confidence: 99%

“…This accident originated from a technology experiment in Chernobyl nuclear power plant which tries to test the available length of a spinning turbine of the electrical power to certain nuclear power plant system (Howieson and Snell, 1987;Sehgal, 2012). Normally, the power would have been reduced to about 30% to conduct the test, but the operators made a mistake and let the power fell to 1%, which is too low to conduct the test.…”

Section: Chernobyl Disastermentioning

confidence: 99%

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Review on Core Degradation and Material Migration Research in Light-Water Reactors

Wang

Shi

et al. 2018

Front. Energy Res.

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Section: Tmi Accidentmentioning

confidence: 99%

Section: Chernobyl Disastermentioning

confidence: 99%

Review on Core Degradation and Material Migration Research in Light-Water Reactors

Wang

Shi

et al. 2018

Front. Energy Res.

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“…Transient corium relocation from the core to the lower head has to be taken into account especially for LWR with heavy reflector (reflector thickness to ablate, stabilization with flooded down-comer, in-core corium pool stratification). Core degradation [10][11][12] is a combination of complex physical phenomena (thermal-hydraulics, oxidation of core materials, loss of core geometry) which could result in the corium pool formation in core and after to its propagation and its relocation in lower head.…”

Section: Introductionmentioning

confidence: 99%

“…So we assume that the core degradation [10][11][12] until the corium pool formation and the corium pool propagation could be modeled separately.…”

Section: Introductionmentioning

confidence: 99%

A simplified geometrical model for transient corium propagation in core for LWR with heavy reflector

Saas

Tellier

Bajard

2017

EPJ Nuclear Sci. Technol.

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Abstract. In the context of the simulation of the Severe Accidents (SA) in Light Water Reactors (LWR), we are interested on the in-core corium pool propagation transient in order to evaluate the corium relocation in the vessel lower head. The goal is to characterize the corium and debris flows from the core to accurately evaluate the corium pool propagation transient in the lower head and so the associated risk of vessel failure. In the case of LWR with heavy reflector, to evaluate the corium relocation into the lower head, we have to study the risk associated with focusing effect and the possibility to stabilize laterally the corium in core with a flooded down-comer. It is necessary to characterize the core degradation and the stratification of the corium pool that is formed in core. We assume that the core degradation until the corium pool formation and the corium pool propagation could be modeled separately. In this document, we present a simplified geometrical model (0D model) for the in-core corium propagation transient. A degraded core with a formed corium pool is used as an initial state. This state can be obtained from a simulation computed with an integral code. This model does not use a grid for the core as integral codes do. Geometrical shapes and 0D models are associated with the corium pool and the other components of the degraded core (debris, heavy reflector, core plate . . . ). During the transient, these shapes evolve taking into account the thermal and stratification behavior of the corium pool and the melting of the core surrounding components. Some results corresponding to the corium pool propagation in core transients obtained with this model on a LWR with a heavy reflector are given and compared to grid approach of the integral codes MAAP4.

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“…In recent years, CFD method has become a choice to analyze the hydrogen risk [4]. Threedimensional transport equations of fluid mechanics can be numerically solved by finite volume method or finite element method in codes.…”

Section: Introductionmentioning

confidence: 99%

Numerical Study on Hydrogen Flow Behavior in Two Compartments with Different Connecting Pipes

Liu

Cao

2017

Science and Technology of Nuclear Installations

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Hydrogen accumulation in the containment compartments under severe accidents would result in high concentration, which could lead to hydrogen deflagration or detonation. Therefore, getting detailed hydrogen flow and distribution is a key issue to arrange hydrogen removal equipment in the containment compartments. In this study, hydrogen flow behavior in local compartments has been investigated in two horizontal compartments. The analysis model is built by 3-dimensional CFD code in Cartesian coordinates based on the connection structure of the Advanced Pressurized Water Reactor (PWR) compartments. It consists of two cylindrical vessels, representing the Steam Generator compartment (SG) and Core Makeup Tank compartment (CMT). With standardturbulence model, the effects of the connecting pipe size and location on hydrogen concentration distribution are investigated. Results show that increasing the diameter of connection pipe (IP) which is located at 800 mm from 150 mm to 300 mm facilitates hydrogen flow between compartments. Decreasing the length of IP which is located at 800 mm from 1000 mm to 500 mm can also facilitate hydrogen flow between compartments. Lower IP is in favor of hydrogen mixing with air in non-source compartment. Higher IP is helpful for hydrogen flow to the non-source term compartment from source term compartment.

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Light Water Reactor Safety

Cited by 62 publications

References 5 publications

Review on Core Degradation and Material Migration Research in Light-Water Reactors

Review on Core Degradation and Material Migration Research in Light-Water Reactors

A simplified geometrical model for transient corium propagation in core for LWR with heavy reflector

Numerical Study on Hydrogen Flow Behavior in Two Compartments with Different Connecting Pipes

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