Development of a control-oriented simulator for a LFR demonstrator

Lorenzi, Stefano; Ponciroli, Roberto; Cammi, Antonio; Bortot, Sara

doi:10.1016/j.nucengdes.2013.04.027

Cited by 8 publications

(5 citation statements)

References 10 publications

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“…Based on the point reactor neutron dynamics with six groups of effective delayed neutron and thermal-hydraulic coupling methods, taking into account the reactivity feedback caused by the temperature change of core coolant, fuel, and cladding, the ordinary differential equations are shown in Eq. 1 to describe the nonlinear model of LFR core (Lorenzi et al, 2013).…”

Section: The Nonlinear Model Of Reactor Corementioning

confidence: 99%

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A Model Predictive Controller for the Core Power Control System of a Lead-Cooled Fast Reactor

Liang

Chen

et al. 2022

Front. Energy Res.

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To study the model predictive control (MPC) for a lead-cooled fast reactor's core power control system (LFR), firstly, the LFR core is established with the state space model. Then, to establish an LFR core power control system, a predictive model controller is used. Finally, the conditions of 20pcm step reactivity and 5% step down of coolant inlet temperature are introduced to study the control characteristic. The maximum overshot (MO) and the transient time are calculated in the time domain, and the stability of the core power control system is analyzed using the Nyquist and Bode diagrams in frequency domains. The result shows that the MPC controller and PID controller are feasible in core power control, and the core power control systems are closed-loop stable systems.

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Section: The Nonlinear Model Of Reactor Corementioning

confidence: 99%

“…LFRs use liquid lead or lead alloy with a high boiling point and high thermal conductivity as a coolant, which not only has a hard neutron energy spectrum but also effectively improves the reactor's safety limit and operation range (Xiuzhong, 2002). Therefore, LFR has a good neutron economy and safety (Lorenzi et al, 2013).…”

Section: Introductionmentioning

confidence: 99%

A Model Predictive Controller for the Core Power Control System of a Lead-Cooled Fast Reactor

Liang

Chen

et al. 2022

Front. Energy Res.

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“…In this approach, the neutron spatial dependence is neglected, and the reactor core is considered as a lumped source of neutrons, where the total power is generated only by fission products and decay heat is not considered. The formulation of the neutron-point kinetics equations is as follows 8 : The neutron density is described by the following equation:…”

Section: Neutronicsmentioning

confidence: 99%

“…In this concern, zero-dimensional models have been proposed to analyze the dynamics and control of different reactors, such as lead-cooled fast reactors (LFR), 8 Triga Mark II, 9 BELLA, 2 small modular reactors (SMR), 10 and boiling water reactors (BWR) reactors. 11 The results have shown good accuracy compared to more complex codes like those mentioned before but having some advantages in terms of fast running, ease on handling, and low computational burden.…”

Section: Introductionmentioning

confidence: 99%

Development of a zero‐dimensional dynamic simulator of a power conversion system with a high‐temperature gas reactor

Juárez‐Martínez

Espinosa-Paredes

2021

Int J Energy Res

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The HTTR-GT/H2 plant is a nuclear power cogeneration plant for hydrogen production. The hydrogen production is based on the thermochemical sulfuriodine cycle able to produce about 30 NM 3 /h of hydrogen and 15 Nm 3 /h of oxygen. The power conversion system consists of a Bryton-cycle helium gas turbine designed to produce 1 MWe electric of power output, and the source of heat is the high temperature engineering test reactor designed by the Japan Atomic Energy Agency. In this work, a preliminary dynamic simulator for the power conversion system was developed. The plant simulator couples the dynamics of the nuclear reactor, the internal heat exchanger, and plant components, such as heat exchangers, coolers, recuperators, compressors, and turbines. Despite the simplicity of modeling, the use of zero-dimensional models showed a good agreement with the reported values, being 0.67% of difference for reactor's power, 0.22% of difference for the coolant outlet temperature, and the differences of the conversion system components compared to the reference ranges between 0.0 and 0.26%.

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“…The most recent research in the field of lead fast reactors secondary loops is presently focused on dynamic modeling for control and stability purpose [9][10][11], investigation on heat exchangers for decay heat removal purpose [12] and experimental investigations of natural circulation [13]. At present, new designs for the leadcooled fast reactors secondary cycles are quite few in literature.…”

Section: Introductionmentioning

confidence: 99%

New steam generation system for lead-cooled fast reactors, based on steam re-circulation through ejector

Damiani

Revetria

2015

Applied Energy

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Development of a control-oriented simulator for a LFR demonstrator

Cited by 8 publications

References 10 publications

A Model Predictive Controller for the Core Power Control System of a Lead-Cooled Fast Reactor

A Model Predictive Controller for the Core Power Control System of a Lead-Cooled Fast Reactor

Development of a zero‐dimensional dynamic simulator of a power conversion system with a high‐temperature gas reactor

New steam generation system for lead-cooled fast reactors, based on steam re-circulation through ejector

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