External heat transfer capability of a submerged SMR containment: The Flexblue case

Santinello, M.; Ricotti, Marco Enrico; Ninokata, Hisashi; Haratyk, Geoffrey; Ingremeau, Jean-Jacques; Gourmel, V.

doi:10.1016/j.pnucene.2016.12.002

Cited by 16 publications

(5 citation statements)

References 19 publications

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“…8. Results of the CFD study about the external HTC in (Santinello et al, 2017), for three uniform internal RC temperatures and T 1 = 35°C. Fig.…”

Section: Resultsmentioning

confidence: 99%

“…Alternatively, if the metal containment is placed into the sea or in an artificial lake, the grace period given by the cooling process is potentially unlimited. Santinello et al (Santinello et al, 2017) performed a numerical investigation about this aspect: they observed that the decay heat cannot influence significantly the temperature of the sink and such heat transfer process is very effective. The water of the sea/lake is a large reservoir acting as a permanent heat sink.…”

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confidence: 99%

“…The results of a previous study (Santinello et al, 2017) (Fig. 8) 408 about the external natural circulation from a submerged horizontal cylindrical containment are employed to define the heat transfer coefficient (HTC).…”

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confidence: 99%

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Long-term decay heat removal in a submerged SMR

Santinello

Ricotti

2019

Annals of Nuclear Energy

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Following the Fukushima-Daiichi nuclear accident in March 2011, innovations are needed to improve the reliability of new generation nuclear power plants toward scenarios where electrical power and ultimate heat sink are lost. This paper describes an integral design and basic passive safety strategy of a Small Modular Reactor (SMR) submerged in the sea or in an artificial lake, then performing a preliminary analysis of the long-term decay heat removal. The analysis considers a pressurized reactor placed in a horizontal cylindrical hull, which is surrounded by the external water. The simulated system is based on the Flexblue concept, developed by French company DCNS (now Naval Group). The object of the investigation is the natural circulation in the submerged containment, which is the key component for the long-term cooling. Following a rupture in the primary circuit, decay heat must be removed according to a fully passive safety strategy for an indefinitely long period. The purpose of this work is to study the effectiveness of a sump natural circulation flow to cool the fuel rods, up to several days after the scram. Decay heat generates steam in the core, which is released in the containment and condensed on the metal surface, transferring the heat to the exterior. Relap5-Mod3.3 has been employed to simulate the accident scenario. Results show the consistency of the safety principles and stimulate experimental investigations. However, the sensitivity analysis identifies the nodalization of the reactor containment as a modeling and numerical issue, deserving further analyses.

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“…8. Results of the CFD study about the external HTC in (Santinello et al, 2017), for three uniform internal RC temperatures and T 1 = 35°C. Fig.…”

Section: Resultsmentioning

confidence: 99%

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confidence: 99%

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Long-term decay heat removal in a submerged SMR

Santinello

Ricotti

2019

Annals of Nuclear Energy

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“…where ρ is the fluid density, unit kg/m 3 ; ρ re f is the reference density, unit kg/m 3 ; → g is the gravitational acceleration vector, unit m/s 2 .…”

Section: Buoyancy Force Modelmentioning

confidence: 99%

“…Marine nuclear power plants have the advantages of high efficiency and economy, which can bring considerable economic benefits to some remote coastal areas lacking resources, and are considered the most ideal energy guarantee for marine development. The containment of marine nuclear power plants mainly has two design schemes: square and cylindrical [1][2][3]. Compared with the square, the cylindrical containment has high space utilization, good structural stability, and strong compression resistance, which provides good protection for nuclear reactors and can be used for deep sea exploration and the development of seabed resources [4].…”

Section: Introductionmentioning

confidence: 99%

Numerical Simulation of Environmental Characteristics of Containment in Severe Accident of Marine Nuclear Power Plant

Xu,

Liu,

Chen

et al. 2023

Energies

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With the reliance on ocean resources, the nuclear power powers have set their sights on marine nuclear power plants to break through the bottleneck of energy supply for the development of ocean resources. In this paper, the computational fluid dynamics software ANSYS CFX 2021 is used to simulate the TOSQAN benchmark experiment. Three different turbulence models, the k−ε model, RNG k−ε model, and SST model, are selected to analyze the adaptability of the turbulence model. The simulation results are compared with the benchmark experimental results, and the selected numerical calculation model is used to analyze the influence of vapor on the pressure, temperature, hydrogen distribution, and hydrogen risk in the containment space when a hypothetical serious accident occurs in a marine nuclear power plant. The results show that the results simulated with the k−ε turbulence model are closer to the benchmark experimental results. Vapor has no obvious effect on the response speed of pressure balance at each position in the closed containment space, and the condensation of the vapor wall can effectively reduce the pressure peak in the closed containment space. The existence of vapor and the increase in vapor concentration will increase the temperature in the closed containment space. The condensation of vapor on the wall surface will cause the temperature in the containment space to have a peak value, which can effectively reduce the temperature in the containment space. Vapor will promote the mixing of gas in the containment space and make the hydrogen distribution tend to be uniform. The presence of vapor and the increase in vapor concentration can reduce the hydrogen risk in the containment space, but the condensation of vapor may increase the hydrogen risk in the containment space.

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