Measurement of Critical Heat Flux in a Candu End Shield Consisting of a Vertical Surface Abutting a Packed Bed of Steel Shielding Balls

Spencer, Justin

doi:10.12943/cnr.2016.00002

Cited by 4 publications

(1 citation statement)

References 30 publications

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“…Fukusako and al. [11], Spencer [12] and Tung and Dhir [13] studied different boiling regimes for different surface materials, shapes and orientations, and different ball materials and sizes. Fukusako and Tung and Dhir showed that CHF increases with ball diameter.…”

Section: Introductionmentioning

confidence: 99%

Coolability of a Corium Pool in a Debris Bed -- Impact of Debris Size, Steam and Liquid Flowrate, Tilting Angle and Pressure on Critical Heat Flux (CHF)

Sartoris,

Garcin,

Fichot

2023

20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

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In case of severe accident in a light water reactor, a debris bed may form in the core and possibly melt, as it happened in TMI-2. Knowledge about the coolability of such molten pool surrounded by debris is crucial to investigate the possibility of stabilizing a part of the fuel inside the vessel. In particular, it is of primary interest to determine the maximum size of a molten pool surrounded by debris which may be stabilized under water. The maximum heat flux (CHF) that may be extracted from the pool boundary by water flowing within the debris bed is a key parameter. A facility was built at IRSN to determine the CHF under various conditions. A heated copper surface simulates the boundary of the pool and is placed in contact with a debris bed (monodisperse steel balls), under water. In this article, we first complete previous work on steam flowrate impact and we show the slight impact of liquid flowrate. We then illustrate the influence of the ball diameter and we compare to the situation of pool-boiling without any debris near the heated plate. All those tests are made for different tilting angles of the plate. In a last part, we study the impact of pressure with an extra pressure level of 1.5 bar abs. As a conclusion of this work and of results previously published, a general CHF correlation depending on the tilting angle and the steam flowrate is derived. An example of the use of this correlation to evaluate the maximum mass of corium pool that can be stabilized under water is given, for some typical reactor conditions.

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Section: Introductionmentioning

confidence: 99%

Coolability of a Corium Pool in a Debris Bed -- Impact of Debris Size, Steam and Liquid Flowrate, Tilting Angle and Pressure on Critical Heat Flux (CHF)

Sartoris,

Garcin,

Fichot

2023

20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

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Coolability of a corium pool in a debris bed – Critical heat flux (CHF) dependency with tilting angle, debris size and steam flowrate

Sartoris

Garcin

Fichot

2023

Nuclear Engineering and Design

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Results of Air Barbotage Experiments Simulating Two-Phase Flow in a CANDU End Shield During In-Vessel Retention

Spencer

2017

Journal of Nuclear Engineering and Radiation Science

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This paper presents the results of experimental investigations into two-phase mass transport in a coarse packed bed representing the Canada Deuterium Uranium (CANDU) end shield. This work contributes to understanding of phenomena impacting in-vessel retention (IVR) during postulated severe accidents in CANDU reactors. The air barbotage technique was used to represent boiling at the calandria tubesheet surface facing the inner cavity of the end shield. Qualitative observations of the near-wall two-phase region were made during air injection. In addition, flow visualization was carried out through the addition of dye to the water. Air flow rate, shielding ball diameter, and cavity dimensions were varied within relevant ranges; and the impact of these parameters on the near-wall region was identified. A brief review of the relevant knowledge base is presented, allowing demonstration of the applicability of the test parameters. The observed phenomena are compared to published results involving similar geometries with capillary porous media.

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Measurement of Critical Heat Flux in a Candu End Shield Consisting of a Vertical Surface Abutting a Packed Bed of Steel Shielding Balls

Cited by 4 publications

References 30 publications

Coolability of a Corium Pool in a Debris Bed -- Impact of Debris Size, Steam and Liquid Flowrate, Tilting Angle and Pressure on Critical Heat Flux (CHF)

Coolability of a Corium Pool in a Debris Bed -- Impact of Debris Size, Steam and Liquid Flowrate, Tilting Angle and Pressure on Critical Heat Flux (CHF)

Coolability of a corium pool in a debris bed – Critical heat flux (CHF) dependency with tilting angle, debris size and steam flowrate

Results of Air Barbotage Experiments Simulating Two-Phase Flow in a CANDU End Shield During In-Vessel Retention

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