Modern design and safety analysis of the University of Florida Training Reactor

Jordan, Kelly A.; Springfels, D.; Schubring, D.

doi:10.1016/j.nucengdes.2015.01.019

Cited by 3 publications

(4 citation statements)

References 4 publications

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“…Besides normal operation, an emergency condition is assumed to happen through a case of reactivity insertion accident, in which the reactivity is increased suddenly due to a control rod ejection. In this study, the excess reactivity of 1.11 $ is assumed to happen, referring to another similar reactor [4].…”

Section: B Methodsmentioning

confidence: 99%

“…Thermal-hydraulic is calculated using mass and energy conservation models, as shown in Eqs. (4)(5) where  is the coolant density, G is mass flux, h is enthalpy, z is position, t is time, lf is mesh height, Af is the outside surface area of the fuel, and q'' is the heat flux. The equations are discretized using the upwind difference and fully implicit schemes [35].…”

Section: B Methodsmentioning

confidence: 99%

“…Since that, strict safety standards have been applied in nuclear-related activities. To avoid direct radiation exposure, reactor simulators have played important roles in nuclear activities, such as reactor design, safety analysis, conducting nuclear facility tests, and educating and training nuclear reactor personnel [4]- [7]. Well-trained reactor operators will determine the safe and efficient operation of nuclear power plants, and it is not an option to conduct the training using a real nuclear power reactor.…”

Section: Introductionmentioning

confidence: 99%

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Improvement of a Code-Based Kartini Reactor Simulator for Education and Training

Sutanto,

Nafisah,

R. Antariksawan

et al. 2023

Int. J. Adv. Sci. Eng. Inf. Technol.

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A code-based Kartini reactor simulator was improved as a facility for the human resource development of a nuclear reactor. The simulator simulates the plant dynamics regarding a change of a control rod position. Reactor operation parameter calculations of the reactor power, coolant flow, and fuel temperatures adopt a one-channel method with assumptions of homogeneous radial power distribution and a cosine function of the axial power distribution. Point reactor kinetics, radial conduction heat transfer, and mass and energy conservation are the calculation code's governing equations. Reactivity feedback due to the coolant density and fuel temperature changes are considered. Reactor pressure is fixed at 1 atm due to an open pool-type research reactor. A graphical user interface was developed to operate the simulator. The operation results of the simulator show that the power calculation agrees well with the experimental data. An accident of excess reactivity due to a control ejection is assumed to happen, causing a positive reactivity insertion of 1.11$. However, the safety criterion of the cladding temperature is satisfied due to the negative reactivity feedback. Besides, early application of 3D virtual reality was carried out to provide an immersive interaction between the users and the virtual Kartini reactor plant. The further development of integrating both the virtual reality and the simulator in the recent Kartini reactor-based internet reactor laboratory is interesting to provide a facility with features of remote as well as immersive education and training.

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Section: B Methodsmentioning

confidence: 99%

Section: B Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Improvement of a Code-Based Kartini Reactor Simulator for Education and Training

Sutanto,

Nafisah,

R. Antariksawan

et al. 2023

Int. J. Adv. Sci. Eng. Inf. Technol.

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“…Examples of codes used for research reactor thermalhydraulic modeling are RELAP5 [21] for the NIST research reactor [22], the IPR-R1 TRIGA Brazilian reactor [23], and the High Flux reactor (HFR) in Netherlands [24]. The PARET code [25] has been used for the McMaster University research reactor [26], the University of Florida Training Reactor [27], and the NUR Algerian research reactor [28] among several others. Also, in many cases, thermal-hydraulic modeling was performed with in-house designed codes, such as the MULCH-II code for the MIT research reactor [29] and PLTEMP for the GRR1 Greek research reactor [30].…”

Section: Thermal-hydraulic Modelingmentioning

confidence: 99%

Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL

Rais

Siefman

Girardin

et al. 2015

Science and Technology of Nuclear Installations

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In order to analyze the steady state and transient behavior of the CROCUS reactor, several methods and models need to be developed in the areas of reactor physics, thermal-hydraulics, and multiphysics coupling. The long-term objectives of this project are to work towards the development of a modern method for the safety analysis of research reactors and to update the Final Safety Analysis Report of the CROCUS reactor. A first part of the paper deals with generation of a core simulator nuclear data library for the CROCUS reactor using the Serpent 2 Monte Carlo code and also with reactor core modeling using the PARCS code. PARCS eigenvalue, radial power distribution, and control rod reactivity worth results were benchmarked against Serpent 2 full-core model results. Using the Serpent 2 model as reference, PARCS eigenvalue predictions were within 240 pcm, radial power was within 3% in the central region of the core, and control rod reactivity worth was within 2%. A second part reviews the current methodology used for the safety analysis of the CROCUS reactor and presents the envisioned approach for the multiphysics modeling of the reactor.

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Development of Kartini Reactor Code to Support Nuclear Training Center and Safety Analysis

Sutanto

Suryana

Syarip

2018

2018 4th International Conference on Science and Technology (ICST)

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Modern design and safety analysis of the University of Florida Training Reactor

Cited by 3 publications

References 4 publications

Improvement of a Code-Based Kartini Reactor Simulator for Education and Training

Improvement of a Code-Based Kartini Reactor Simulator for Education and Training

Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL

Development of Kartini Reactor Code to Support Nuclear Training Center and Safety Analysis

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