Multi-Physics Model Development for Polonium Transport Behavior in a Lead-Cooled Fast Reactor

Lilin, Deng; Wang, Yuqing; Zhai, Zian; Huang, Bochen; Wu, Jiewei; He, Jianbo; Ni, Muyi

doi:10.3389/fenrg.2021.711916

Cited by 3 publications

(3 citation statements)

References 15 publications

(22 reference statements)

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“…replacement of components), and to the public in case of accident. The 210 Po accumulated in the coolant is mainly restrained as PbPo; only a very minor part (≈10 −9 in [26]) could evaporate into cover gas. The contamination in the air is determined by the aerosol deposition, the surface contamination and the aerosol resuspension.…”

Section: Safety Considerationsmentioning

confidence: 99%

Production and transport modelling of Po-210 in DEMO reactor

Chiovaro¹,

Quartararo²,

Basile³

et al. 2022

Nucl. Fusion

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One of the generic designs of the nuclear fusion DEMO reactor proposed by the EUROfusion consortium foresees the development of a tritium Breeding Blanket (BB) relying on the use of the liquid-metal PbLi eutectic alloy as both neutron multiplier and tritium breeder, namely the Water-Cooled Lithium Lead (WCLL) BB, whose strengths and weaknesses are well known. This paper focuses the attention on one of the possible disadvantages of such a technology: the production of the highly radiotoxic radionuclide 210Po, which could become a safety issue to be accounted for. The 210Po concentration within the PbLi circuit has been assessed by solving a modified version of Bateman’s equations to consider the alloy circulation, so a one-dimensional convective fluid-dynamic model has been set up. Nuclear quantities have been evaluated by Monte Carlo neutron transport analyses using MCNP code and adopting a fully heterogeneous model of DEMO equipped with the WCLL BB. Moreover, rough sensitivity analyses have been performed to assess the influence on the results of the uncertainties related to the 209Bi radiative-capture cross section and the initial concentration of this nuclide which is present in the PbLi as an impurity. Results obtained have been critically discussed and some safety issues have been addressed to evaluate the possible hazard in case of a leak of PbLi accident.

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Section: Safety Considerationsmentioning

confidence: 99%

Production and transport modelling of Po-210 in DEMO reactor

Chiovaro¹,

Quartararo²,

Basile³

et al. 2022

Nucl. Fusion

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“…To resolve this problem, a porous medium approximation was used to model core and HX to match the expected pressure drops, which had shown good reliability according ref. [9,10].…”

Section: Operation Condition Of Typical Lfrmentioning

confidence: 99%

“…And a reference case was utilized to provide a baseline model. According to the design of MYRRHA [10,11], the porosity of reactor core is set to 0.3 and the porosity of HX is set to 0.62 in this baseline model, where permeability means the resistance of fluid flowing through porous medium in three dimensions. And a lower permeability means a stronger resistance.…”

Section: Operation Condition Of Typical Lfrmentioning

confidence: 99%

Prediction of Global Corrosion and Corrosion Products Behavior in the Primary Circuit of LBE Fast Reactor

Wu¹,

Wu²,

Wang³

et al. 2021

Preprint

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For better understanding the corrosion and corrosion products behavior in the primary circuit of lead-bismuth eutectic (LBE) coolant reactor, the concentration distribution of soluble impurities and the transport of solid particles are investigated through finite-element method. An axisymmetric model of the primary circuit of LBE reactor was constructed to accelerate the calculation the thermal hydraulic filed of circuit. The saturation concentration of solute Fe, Cr and Ni in LBE coolant are identified through the equilibrium of their oxides and PbO. And the very different saturation concentrations of Fe/Cr/Ni in LBE will lead to significant element selective corrosion. The migration of solid oxides particles in the primary circuit is also investigated by the Euler-Lagrange tracing model. The simulation shows that driving force for the movement of particles &gt;100 μm is buoyancy, which lets particles float on a free surface, while particles &lt;10 μm tend to suspend in coolant. However, the behavior of particles also depends on the formation position, the particles formed above the core have the high possibility of re-entering in the core.

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