Transfer Function Modeling of Zero-Power Dynamics of Circulating Fuel Reactors

2010 ◽  
Vol 133 (5) ◽  
Author(s):  
A. Cammi ◽  
V. Di Marcello ◽  
C. Guerrieri ◽  
L. Luzzi
Keyword(s):  
Molten Salt ◽  
Transfer Functions ◽  
Dynamic Performance ◽  
National Laboratory ◽  
Power Dynamics ◽  
Neutron Density ◽  
Preliminary Evaluation ◽  
Molten Salt Reactor ◽  
General Validity ◽  
Oak Ridge

In this paper, the zero-power behavior of circulating fuel reactors (CFRs) has been investigated by means of a zero-dimensional neutron kinetics model that provides a simplified but useful approach to the simulation of the dynamics of this class of nuclear reactors. Among CFRs, the most promising is the molten salt reactor (MSR), which is one of the six innovative concepts of reactor proposed by the “Generation IV International Forum” for future nuclear energy supply. One of the key features of CFRs is represented by the fission material, which is dissolved in a liquid mixture that serves both as fuel and coolant. This causes a relevant coupling between neutronics and thermo-hydrodynamics, so that fuel velocity plays a relevant role in determining the dynamic performance of such systems. In the present study, a preliminary model has been developed that is based on the zero-power kinetics equations (i.e., reactivity feedbacks due to temperature change are neglected), modified in order to take into account the effects of the molten salt circulation on the drift of delayed neutron precursors. The system dynamic behavior has been analyzed using the theory of linear systems, and the transfer functions of the neutron density with respect to both reactivity and fuel velocity have been calculated. The developed model has been assessed on the basis of the available experimental data from the molten salt reactor experiment (MSRE) provided by the Oak Ridge National Laboratory. The results of the present work show that the developed simplified theoretical model is well descriptive of the MSRE zero-power dynamics, allowing a preliminary evaluation of the effects due to the circulation of the fuel salt on the neutronics of the system. Moreover, the model is of general validity for any kind of CFRs, and hence is applicable to study other MSR concepts in order to have some indications on the control strategy to be adopted in the MSR development envisaged by Generation IV.

A Preliminary Approach to the Dynamic Behaviour of Circulating Fuel Reactors for Generation IV

2009 ◽  
Author(s):  
Valentino Di Marcello ◽  
Antonio Cammi ◽  
Lelio Luzzi
Keyword(s):  
Molten Salt ◽  
Dynamic Behaviour ◽  
National Laboratory ◽  
Preliminary Evaluation ◽  
Molten Salt Reactor ◽  
General Validity ◽  
Primary Loop ◽  
Oak Ridge ◽  
Reactor Stability ◽  
Independent Zero

A preliminary approach to the simulation of the dynamics of the Circulating Fuel Reactors (CFR) is presented in this paper. Among CFRs, the most promising is the Molten Salt Reactor (MSR), which is one of the “Generation IV International Forum” concepts. Assuming the space-independent zero-power kinetics equations modified in order to take into account the coupling with the molten salt circulation, the dynamic behaviour has been analyzed by means of the transfer function of the system (core + external primary loop). A very simple model is proposed that has been validated on the basis of the experimental data from the Molten Salt Reactor Experiment (MSRE) performed at the Oak Ridge National Laboratory (ORNL); after the validation, it has been applied to study the effects of the coolant velocity on the reactor stability, taking into account the circulation time in the core as well as in the external primary loop. Even if the material properties adopted in the analyses refer to the values encountered in the MSRE, the dynamic model is of more general validity for nuclear reactors with circulating fuels. The results of the present work allow a preliminary evaluation of the coupling between the point neutron kinetics and the velocity of the circulating fuel, and they also give a first indication on the control strategy to be adopted in the current development of MSRs for Generation IV.

A Review of Molten Salt Reactor Xenon Analysis Literature

2019 ◽  
Vol 6 (1) ◽  
Author(s):  
T. J. Price ◽  
O. Chvala
Keyword(s):  
Molten Salt ◽  
Void Fraction ◽  
Experimental Work ◽  
National Laboratory ◽  
A Priori ◽  
Molten Salt Reactor ◽  
Oak Ridge ◽  
Sensitive Dependence ◽  
Oak Ridge National Laboratory ◽  
Work Done

Abstract This paper presents a review of xenon analyses literature related to molten salt reactors (MSRs). A brief primer of reactor xenon theory is presented for fluid fueled reactors. A review of xenon analysis literature is presented for both the work done by the Oak Ridge National Laboratory, and the later work in academia. A review of experimental work is presented. The paper concludes with describing some of the difficulties in establishing a priori xenon models and includes a commentary on the sensitive dependence of the molten salt reactor xenon behavior on the circulating void fraction.

scholarly journals Batch-Scale Hydrofluorination of Li27BeF4 to Support Molten Salt Reactor Development

2015 ◽  
Vol 1 (4) ◽  
Author(s):  
Brian C. Kelleher ◽  
Kieran P. Dolan ◽  
Paul Brooks ◽  
Mark H. Anderson ◽  
Kumar Sridharan
Keyword(s):  
Molten Salt ◽  
Nuclear Reactor ◽  
National Laboratory ◽  
The United States ◽  
Hydraulic Testing ◽  
Molten Salt Reactor ◽  
Fluoride Salt ◽  
Oak Ridge ◽  
University Of Wisconsin ◽  
Analysis Process

Li 2 BeF 4 , or flibe, is the primary candidate coolant for the fluoride-salt-cooled high-temperature nuclear reactor (FHR). Kilogram quantities of pure flibe are required for repeatable corrosion tests of modern reactor materials. This paper details fluoride salt purification by the hydrofluorination–hydrogen process, which was used to regenerate 57.4 kg of flibe originating from the secondary loop of the molten salt reactor experiment (MSRE) at Oak Ridge National Laboratory (ORNL). Additionally, it expounds upon necessary handling precautions required to produce high-quality flibe and includes technological advancements which ease the purification and analysis process. Flibe batches produced at the University of Wisconsin are the largest since the MSRE program, enabling new corrosion, radiation, and thermal hydraulic testing around the United States.

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