Simulated transient dynamics and heat transfer characteristics of the water boiler nuclear reactor – SUPO – with cooling coil heat extraction

Buchan, Andrew G.; Pain, Christopher C.; Goddard, A.J.H.; Eaton, M.D.; Gomes, Jefferson L. M. A.; Gorman, Gerard J.; Cooling, C.M.; Tollit, Brendan; Nygaard, E.T.; Glenn, Dennis E.; Angelo, P.L.

doi:10.1016/j.anucene.2012.03.027

Cited by 9 publications

(6 citation statements)

References 10 publications

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“…The first benchmarking exercise was performed using available results of four critical experiments performed at the Russian Research Center "Kurchatov Institute" [18] in order to validate that the developed models of AHR with MCNP and ANSYS-CFX are adequate for studies of aqueous fuel solutions. In the second benchmarking exercise, the geometrical and material configuration of the SUPO reactor was modeled in ANSYS-CFX and the results of the calculation compared with those available in the scientific literature [22,25]. The results obtained during these benchmarking exercises have been published and comprehensively discussed in [4,[15][16][17].…”

Section: Benchmarking Exercisesmentioning

confidence: 99%

New advances in the computational simulation of Aqueous Homogeneous Reactor for medical isotopes production

Pérez¹,

Pardo²,

Pérez³

et al. 2021

Braz. J. Rad. Sci.

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Aqueous Homogeneous Reactors (AHRs) or simply solution reactors present nowadays a promising alternative to produce medical isotopes, especially 99Mo. The AHR medical production concept has been proposed to produce medical isotopes directly in the fuel solution, resulting in a potentially competitive alternative in comparison with the solid target irradiation method in heterogeneous reactors. Furthermore, the utilization of AHRs for medical isotopes production has been strengthened because of the successful operation of the ARGUS reactor since 1981 and its conversion to low-enriched uranium (LEU) fuel during 2012-2014. Those successes positively influenced in the decisions to construct a Proof-Of-Concept production site based on the ARGUS operational experience in Sarov (500 km from Moscow) and to restore the Argus-FTI at the Umarov Physical and Technical Institute in Dushanbe, Tajikistan. However, demonstrating the viability of the AHRs for medical isotopes requires solving several significant challenges related with the safe operation of these reactors. Consequently, not only for the design, licensing and safe operation of the AHRs, but also for the prediction of accident scenarios it is very important to be able to simulate and predict the behavior of the fuel solutions through a group of relevant physical parameters. Accordingly, this paper aims to show the advances made to improve the predictive capabilities during the multi-physics computational modeling of AHRs.

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Section: Benchmarking Exercisesmentioning

confidence: 99%

New advances in the computational simulation of Aqueous Homogeneous Reactor for medical isotopes production

Pérez¹,

Pardo²,

Pérez³

et al. 2021

Braz. J. Rad. Sci.

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show abstract

“…It shows how domains containing internal bodies with intricate detail can be resolved efficiently by avoiding the issues already highlighted regarding the need for large initial meshes to capture geometric detail. In this demonstration the SUPO reactor is resolved (this is an eigenvalue problem involving equations 2 and 4), a picture and CAD design using Cubit [39] is presented in figure 14, other views can be found in [20,40]. As this problem has been resolved previously in [20,40] the full details of the geometry and materials will not be repeated here.…”

Section: Numerical Example 3: the Supo Reactormentioning

confidence: 99%

“…In this demonstration the SUPO reactor is resolved (this is an eigenvalue problem involving equations 2 and 4), a picture and CAD design using Cubit [39] is presented in figure 14, other views can be found in [20,40]. As this problem has been resolved previously in [20,40] the full details of the geometry and materials will not be repeated here. However the reactor had a spherical core (approximately 30cm in radius) containing a uranium nitrate liquid fuel that was contained within steel vessel, and surrounded by graphite reflector.…”

Section: Numerical Example 3: the Supo Reactormentioning

confidence: 99%

A combined immersed body and adaptive mesh method for simulating neutron transport within complex structures

Buchan

Dargaville

Pain

2019

Annals of Nuclear Energy

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This article describes a new adaptive immersed body method for the efficient and accurate modelling of neutron transport within geometrically complex domains. It combines two techniques of immersed body projections and self-adaptive mesh refinement to form a unique method that can efficiently resolve problems that contain complex internal structures. The approach allows complete freedom of where mesh resolution is placed and the meshes, which do not need to conform to the problem structure, are optimised for resolving the physics of the problem.

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“…(4) A growing number of scientific papers on this subject each year, just to mention a few [8], [9], [18], [19], [10]- [17]. In addition, a significant number of technical reports, conference presentations and others are also evidence of the existing interest in this technology.…”

Section: Introductionmentioning

confidence: 99%

Multi-physics evaluation of the steady-state operation of an Aqueous Homogeneous Reactor for producing Mo-99 for the Brazilian demand

Pérez

Pardo

et al. 2021

International Journal of Thermodynamics

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The studies summarized in this paper aims to predict the steady state operation of a low-enriched uranium fuel ARGUS type aqueous homogeneous reactor for producing 99 Mo to meet the domestic demand of Brazil through a coupled multi-physics (Neutronics + Thermal-hydraulics) evaluation. The coupled multi-physics evaluation included aspects related to the neutronic behavior such as fission induced energy deposition profile, medical isotopes production; and the thermal-hydraulic behavior such as temperature, velocities and gas volume fraction profiles. The methodology followed for the multi-physics and multi-scale coupling of the neutronic and thermal-hydraulic codes (MCNP + ANSYS-CFX), discussed in detail in this paper, represent one of the main outcomes of the current study. The methodology was tested for two different operating configurations of the ARGUS reactor, the original high-enriched uranium configuration used since 1981, and the new low-enriched uranium configuration after the conversion process during 2012-2014. The calculations carried out showed that the reactor, in the studied configuration, is able to produce 246.5 six days Curie of 99 Mo in operation cycles of five days. Which is equivalent to more than a third of the estimated Brazilian demand for 2025.

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Simulated transient dynamics and heat transfer characteristics of the water boiler nuclear reactor – SUPO – with cooling coil heat extraction

Cited by 9 publications

References 10 publications

New advances in the computational simulation of Aqueous Homogeneous Reactor for medical isotopes production

New advances in the computational simulation of Aqueous Homogeneous Reactor for medical isotopes production

A combined immersed body and adaptive mesh method for simulating neutron transport within complex structures

Multi-physics evaluation of the steady-state operation of an Aqueous Homogeneous Reactor for producing Mo-99 for the Brazilian demand

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