FMSR: A code system for in-core fuel management calculation of aqueous homogeneous solution reactor

Li, Yunzhao; Wu, Hongchun; Cao, Liangzhi; Chen, Qichang; Lu, Hongbin; Peng, Sitao; Song, Xiaoming; Yang, Dong

doi:10.1016/j.nucengdes.2009.10.028

Cited by 7 publications

(2 citation statements)

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“…In this process are produced gas bubbles, composed by hydrogen and oxygen in the UO2SO4 solutions [2]. The production of radiolytic gas bubbles and its influence in the operational behavior of AHR has been previously studied [17]- [19], [29]- [31], and concluded that the production of medical isotopes in solution reactors may not be accomplished without mitigation of its effects [32]. Evaluating the effects produced by radiolytic gas bubble formation require to know two important parameters, (1) the bubble size and (2) the total gas bubbles volume.…”

Section: Figure 3 Ahr Conceptual Design Model With the Two Coiled Cooling Pipes And The Fuel Solutionmentioning

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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Section: Figure 3 Ahr Conceptual Design Model With the Two Coiled Cooling Pipes And The Fuel Solutionmentioning

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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“…Mainly, three types of aqueous fuel solutions have been considered or used for 99 Mo production using an AHR: (1) In AHR, because of the radiolytic decomposition of the fuel solution, bubbles will be produced. The production of these bubbles will play an important role in the reactor behavior because of the diminution of the density of the fuel solution and the expansion of fuel solution volume [8,9]. Therefore, the rate and composition of these bubbles must be considered for the design and operation of AHR.…”

Section: Introductionmentioning

confidence: 99%

Thermal-Hydraulics Study of a 75 kWth Aqueous Homogeneous Reactor for ⁹⁹Mo Production

Pérez

Lorenzo

Garcia

et al. 2015

Journal of Thermodynamics

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Tc99m is a very useful radioisotope, which is used in nearly 80% of all nuclear medicine procedures. Tc99m is produced from 99Mo decay. A potentially advantageous alternative to meeting current and future demand for 99Mo is the use of Aqueous Homogeneous Reactors (AHR). In this paper, a thermal-hydraulics study of the core of a 75 kWth AHR conceptual design based on the ARGUS reactor for 99Mo production is presented. As the ARGUS heat removal systems were designed for working at 20 kWth, the main objective of the thermal-hydraulics study was evaluating the heat removal systems in order to show that sufficient cooling capacity exists to prevent fuel solution overheating. The numerical simulations of an AHR model were carried out using the Computational Fluid Dynamic (CFD) code ANSYS CFX 14. Evaluation shows that the ARGUS heat removal systems working at 75 kWth are not able to provide sufficient cooling capacity to prevent fuel solution overheating. To solve this problem, the number of coiled cooling pipes inside the core was increased from one to five. The results of the CFD simulations with this modification in the design show that acceptable temperature distributions can be obtained.

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Optimization study and neutronic design calculations of LEU fuelled homogeneous aqueous solution nuclear reactors for the production of short lived fission product isotopes

Mahmood¹,

Iqbal²

2012

Annals of Nuclear Energy

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FMSR: A code system for in-core fuel management calculation of aqueous homogeneous solution reactor

Cited by 7 publications

References 1 publication

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

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

Thermal-Hydraulics Study of a 75 kWth Aqueous Homogeneous Reactor for ⁹⁹Mo Production

Optimization study and neutronic design calculations of LEU fuelled homogeneous aqueous solution nuclear reactors for the production of short lived fission product isotopes

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FMSR: A code system for in-core fuel management calculation of aqueous homogeneous solution reactor

Cited by 7 publications

References 1 publication

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

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

Thermal-Hydraulics Study of a 75 kWth Aqueous Homogeneous Reactor for 99Mo Production

Optimization study and neutronic design calculations of LEU fuelled homogeneous aqueous solution nuclear reactors for the production of short lived fission product isotopes

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Thermal-Hydraulics Study of a 75 kWth Aqueous Homogeneous Reactor for ⁹⁹Mo Production