A refined time-delay modeling of the molten salt reactor dynamics

Zarei, Mostafa

doi:10.1016/j.pnucene.2019.103102

Cited by 3 publications

(2 citation statements)

References 15 publications

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“…The temperature of the coolant salt in the shell side was assumed to be constant at 450 ℃ [20], [21]. For the fuel salt temperature in the heat exchanger, the heat transfer equation can be written as:…”

Section: Thermal-hydraulics Modelmentioning

confidence: 99%

Fuel Flow Modeling under Thermal Fluidics Considerations within Operational Domains of Molten Salt Reactors

Abuqudaira,

Tsvetkov,

Sabharwall

2023

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Molten Salt Reactors (MSRs) offer significant versatility supported by their design flexibility and safety advantages due to high temperatures, design customization capabilities, strong negative reactivity feedback effects, and salt chemistry characteristics. Different control schedules and different mass flow rates in the MSR primary systems impact neutronics and thermal hydraulics coupling. The result is twofold. First, it leads to adaptability in various applications when the customization of a MSR unit is desired. Second, it calls for the quantification of dynamics and safety characteristics to assess the operational domain and make sure reactor stability and inherent safety characteristics are maintained. This paper provides an in-depth transient analysis of the operational implications of MSRs having heatgenerating fuel and heat-transporting salt mixed forming liquid fuel salts contained within primary systems. A coupling model was developed to simulate fuel flow in molten salt reactors. A zerodimensional reactor kinetics model was used with a one-dimensional heat transfer model in the reactor core. The temperature reactivity feedbacks of the fuel salt resulting from the thermal-hydraulics model were used in the reactor kinetics model to complete the coupled code. The model was first validated with the experimental results from the Molten Salt Reactor Experiment (MSRE). Then, it was applied to simulate the Molten Salt Breeder Reactor (MSBR) response at steady state and transients. The developed model was shown to be a suitable tool for the dynamic analysis of molten salt reactors.

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Section: Thermal-hydraulics Modelmentioning

confidence: 99%

Fuel Flow Modeling under Thermal Fluidics Considerations within Operational Domains of Molten Salt Reactors

Abuqudaira,

Tsvetkov,

Sabharwall

2023

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“…Related equations are expressed as follows. The equations are taken after or further simplified from the models presented in the references as follows [21,22].…”

Section: Heat Transfer Modelmentioning

confidence: 99%

Proposal of Application of a Simple Analysis Code DYMOS for Accident Analyses of Molten Salt Reactors

Shimazu,

Yoshioka,

Ogasawara

2023

JENRR

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The Molten Salt Reactor (MSR) possesses unique characteristics, including the circulation of liquid fuel salt in-core and ex-core, and the absence of cladding tubes of fuel rods. To perform safety analyses for accidents and transients, the selection of appropriate models is crucial. Proposed models vary from the coupling of a three-dimensional (3-D) nuclear reactor model and a detailed thermal/hydraulic (T/H) model to a simple point reactor model coupled with a lumped parameter model of the T/H system. The authors have been investigating the development of a simple and accurate model that can be utilized during the design stage and licensing evaluation, while also providing transparency, which means that models can be easily understandable by experts and reproduced in licensing evaluation. Given the distinctive features of the MSR, the peak heat flux or fuel cladding peak temperature is not a requirement. Instead, the most decisive parameter for safety evaluations is the fuel salt temperature in the fuel salt boundary. As demonstrated in this paper, the outlet of the MSR core consistently displays the highest temperature.Based on the afore-mentioned prospects for both nuclear and T/H systems, the authors have developed a simple safety and transient analysis code for MSR (DYMOS). The DYMOS code has been verified for MSRE experiments, as described in this paper. However, the previous verification was limited to small experimental MSRs, and there is a lack of verification for large reactor systems. This paper shows that the DYMOS code is applicable to these larger reactors. In other words, the main objective of this article is not to claim the originality of the model of DYMOS code, but to propose applicability of such simple code to large reactor systems.

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Design of optimal fractional order fuzzy PID controller based on cuckoo search algorithm for core power control in molten salt reactors

Karahan

2021

Progress in Nuclear Energy

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A refined time-delay modeling of the molten salt reactor dynamics

Cited by 3 publications

References 15 publications

Fuel Flow Modeling under Thermal Fluidics Considerations within Operational Domains of Molten Salt Reactors

Fuel Flow Modeling under Thermal Fluidics Considerations within Operational Domains of Molten Salt Reactors

Proposal of Application of a Simple Analysis Code DYMOS for Accident Analyses of Molten Salt Reactors

Design of optimal fractional order fuzzy PID controller based on cuckoo search algorithm for core power control in molten salt reactors

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