Control System of a Super Fast Reactor with Single Flow Pass Core

Sutanto Sutanto, Jianhui Wu

Abstract


The one-pass supercritical pressure light water fast reactor has different core structure from that of the two-pass cooling type one. The distance between inlet and outlet channels of the one-pass supercritical pressure light water fast reactor is shorter with less core water inventory due to the removal of the gap channels. Its responses to a perturbation are similar to those of the two pass core. However, change of the outlet temperature regarding to a perturbation of power to flow ratio in the one-pass cooling type fast reactor is larger. It is important to suppress the change as small as possible to keep the integrity of the reactor structure. Early designs of power and pressure control systems of a supercritical pressure light water fast reactor are applicable to control the power and pressure parameters, but it is not for the early outlet temperature control system which considered only the outlet temperature deviation as the feedback. An improved outlet temperature control system which considers both the signals of outlet temperature and power deviations as the control feedbacks can be applied in the one-pass cooling-type fast reactor with adjustment on the control’s parameters. Optimized control’s parameters can suppress the change of the outlet temperature significantly without oscillation. By using the control system, responses of the one-pass supercritical pressure light water fast reactor to the designated perturbations satisfy the criteria.

Keywords


fast reactor; one-pass; control; temperature change; criteria.

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References


Y. Oka, S. Koshizuka, Y. Ishiwatari, A. Yamaji, Super Light Water Reactors and Super Fast Reactors, Springer New York Dordrecht Heidelberg London, 2010.

T. Schulenberg, L. K.H. Leung, Y. Oka,â€Review of R&D for Supercritical Water Cooled Reactorsâ€, J. of Progress in Nuclear Energy, Vol. 77, 2014, p. 282-299.

Y. Oka, H. Mori, Supercritical Pressure Light Water Cooled Reactors, Springer Tokyo Heidelberg New york Dordrecht London, 2014.

T. Jevremovic, Y. Oka, S. Koshizuka, “Conceptual Design of an Indirect-cycle, Supercritical Steam Cooled Fast Breeder Reactor with Negative Coolant Void Reactivity Characteristicsâ€, J. Ann. Nucl. Energy, Vol. 20, 1993, p. 305-313.

T Jevremovic, Y. Oka, S. Koshizuka, “Core Design of a Direct-cycle Supercritical-Water-Cooled Fast Breeder Reactor, J. Nucl. Technol, Vol. 108, 1994, p. 24-32.

T. Mukohara, S. Koshizuka, Y. Oka, “Core Design of a High-Temperature Fast Reactor Cooled by Supercritical Light Waterâ€, J. Ann. Nucl. Energy, Vol. 26, 1999, p. 1423-1436.

Y. Oka, S. Koshizuka, “Design Concept of Once-Through Cycle Supercritical-Pressure Light Water Cooled Reactorsâ€, SCR-2000, Nov. 6-8, 2000, Tokyo.

L. Cao, Y. Oka, Y. Ishiwatari, Z. Shang, “Core Design and Subchannel Analysis of a Superfast Reactorâ€, J. Nucl. Sci. Technol, Vol. 45, 2008, p. 138-148.

J. Yoo, Y. Ishiwatari, Y. Oka, J. Liu, “ Conceptual Design of Compact Supercritical Water-Cooled Fast Reactor with Thermal Hydraulic Couplingâ€, J. Ann. Nucl. Energy, Vol. 33, 2006, p. 945-956.

Q. Liu, Y. Oka, “Core Design for Super Fast Reactor with All Upward Flow Core Coolingâ€, J. Ann. Nucl. Energy, Vol. 57, 2013, p. 221-229.

Q. Liu, Y. Oka, “Improvements ofTwo-pAss Core Design for Super Fast Reactor,†J. Ann. Nucl. Energy, Vol. 69, 2014, p. 108-115.

S. Ikejiri, Y. Ishiwatari, Y. Oka, “Safety Analysis of a Supercritical-Pressure Water-Cooled Fast Reactor under Supercritical Pressureâ€, J. Nucl. Eng. Design, Vol 240, 2010, p. 1218-1228.

T. Kamata, Y. Oka, “Total Loss of Flow Accident Characteristics of Super FR with New Coolant Flowâ€, J. Nucl. Eng. Design, Vol. 257, 2013, p. 155-160.

H. Li, Y. Oka, Y. Ishiwatari, “Safety Analysis of a Supercritical Water Cooled Fast Reactor with All-Upward Two-Pass Flowâ€, J. Ann. Nucl. Energy,Vol. 59, 2013, p. 1-9.

T. Nakatsuka, Y. Oka, S. Koshizuka, “Control of a Fast Reactor Cooled by Supercritical Light Waterâ€, J. Nucl. Technol., Vol. 121, 1998, p. 81-92.

Y. Ishiwatari, C. Peng, S. Ikejiri, Y. Oka, “Improvement of Feedwater Controller for The Super Fast Reactorâ€, J. Nucl. Sci. Technol., Vol. 47, No. 12, 2010, p. 1155-1164.

Sutanto, Y. Oka, “Time Dependent Start-up Thermal Analylis of a Super Fast Reactorâ€, J. Nucl. Eng. Design, Vol. 263, 2013, p. 129-137.

Q. Liu, Y. Oka, “Single Pass Core Design for a Super Fast Reactorâ€, J. Ann. Nucl. Energy, Vol. 80, 2015, p. 451-459.

Sutanto, Y. Oka, “Safety Analysis of a Super Fast Reactor with Single Flow Pass Coreâ€, Trans. of The American Nuclear Society, Vol. 109, Washington DC., November 10-14, 2013, p. 1092-1094.

Sutanto, Y. Oka,â€Accident and Transient Analysis of a Super Fast Reactor with Single Flow Pass Coreâ€, J. Nucl. Eng. Design, Vol. 273, 2014, p. 165-174.

Sutanto, Y. Oka, “Analysis of Anticipated Transient Without Scram of a Super Fast Reactor with Single Flow Pass Coreâ€, J. Ann. Nucl. Energy, Vol. 75, 2015, p. 54-63.

Sutanto, Y. Oka, “Passive Safety System of a Super Fast Reactorâ€, J. Nucl. Eng. Design, Vol. 289, 2015, p. 117-125.

M. Zarei, “A Multi-point Kinetics Based MIMO-PI Control of Power in PWR Reactorsâ€, J. Nucl. Eng. Design, Vol. 328, 2018, p. 283-291

S.M.H. Mousakazemi, N. Ayoobian, G. R. Ansarifar, “Control of The Reactor Core Power in PWR Using Optimized PID Controller with The Real-Coded GAâ€, Annals of Nucl. Energy, Vol. 118, 2018, p. 107-121.




DOI: http://dx.doi.org/10.18517/ijaseit.8.5.6516

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