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Featured researches published by Q. Lv.


Nuclear Technology | 2016

Experimental Study of DRACS Thermal Performance in a Low-Temperature Test Facility

Q. Lv; Hsun Chia Lin; Shanbin Shi; Xiaodong Sun; Richard N. Christensen; Thomas E. Blue; Graydon L. Yoder; Dane F Wilson; Piyush Sabharwall

Abstract The Direct Reactor Auxiliary Cooling System (DRACS) is a passive decay heat removal system proposed for the Fluoride salt–cooled High-temperature Reactor (FHR) that combines coated particle fuel and a graphite moderator with a liquid fluoride salt as the coolant. The DRACS features three coupled natural circulation/convection loops, relying completely on buoyancy as the driving force. These loops are coupled through two heat exchangers, namely, the DRACS heat exchanger (DHX) and the natural draft heat exchanger (NDHX). To experimentally investigate the thermal performance of the DRACS, a scaled-down low-temperature DRACS test facility (LTDF) has been constructed. The design of the LTDF is obtained through a detailed scaling analysis based on a 200-kW prototypic DRACS design developed at The Ohio State University. The LTDF has a nominal power capacity of 6 kW. It employs water pressurized at 1.0 MPa as the primary coolant, water near the atmospheric pressure as the secondary coolant, and ambient air as the ultimate heat sink. Three accident scenarios simulated in the LTDF are discussed in this paper. In the first scenario, startup of the DRACS system from a cold state is simulated with no initial primary coolant flow. In the second scenario, a reactor coolant pump trip process is studied, during which a flow reversal phenomenon in the DRACS primary loop occurs. In the third scenario, the pump trip process is studied with a simulated intermediate heat exchanger in operation during the simulated core normal operation. In all scenarios, natural circulation flows are developed as the transients approach their quasi steady states, demonstrating the functionality of the DRACS. The accident scenarios in the prototypic FHR design corresponding to the simulated ones in the LTDF are also predicted by following a scaling-up process. The predictions show that at any time during the simulated transient, the salt temperatures will be higher than their melting temperatures and that therefore there will be no issue of salt freezing in the three projected accident scenarios. However, the scaled-up primary salt temperatures indicate that the prototypic DHX may have been undersized and may need to be redesigned.


2013 21st International Conference on Nuclear Engineering, ICONE 2013 | 2013

Design of Fluidic Diode for a High-Temperature DRACS Test Facility

Q. Lv; M. Chen; Xiaodong Sun; Richard M. Christensen; Thomas E. Blue; Graydon L. Yoder; Dane F Wilson; Piyush Sabharwall

The Direct Reactor Auxiliary Cooling System (DRACS) is a passive heat removal system proposed for the Advanced High-Temperature Reactor (AHTR) that combines the coated particle fuel and graphite moderator with a liquid fluoride salt as the coolant. The DRACS features three coupled natural circulation/convection loops relying completely on buoyancy as the driving force. A fluidic diode has been proposed in the DRACS primary loop to maintain the passive feature. Fluidic diodes are passive flow control devices with low flow resistance in one direction and high flow resistance in the opposite direction. The fluidic diode is orientated such that during reactor normal operation the primary salt flow in the DRACS is restricted, thus preventing excessive heat loss from the reactor to the DRACS. However, when the DRACS is functioning during reactor accidents, the primary salt flow is in the forward flow direction of the diode that features low flow resistance.To investigate the reliability and thermal performance of the DRACS, a high-temperature DRACS test facility (HTDF) is being designed and constructed at The Ohio State University (OSU). In this HTDF, a conventional vortex diode has been proposed. In this paper, a detailed design process of the vortex diode for the HTDF is presented. Design parameters, such as the desired flow rates in and pressure drops across the fluidic diode, were first determined for both the forward and reverse flow directions, following which was the parametric CFD study of multiple vortex diodes with variant nozzle size, chamber size, and inlet flow rates. Flow structures inside the diode, and the effects of the nozzle size, chamber size, and Reynolds number on the Euler number were examined for both flow directions. Correlations of the forward and reverse Euler numbers and the diodicity were developed and used to develop a vortex diode design that would be applicable to the HTDF.Copyright


Transactions of the american nuclear society | 2011

A modular design of a direct reactor auxiliary cooling system for AHTRs

Xia Wang; Q. Lv; Xiaodong Sun; Richard N. Christensen; Thomas E. Blue; Graydon L. Yoder; Dane F Wilson; Piyush Sabharwall


Annals of Nuclear Energy | 2015

DRACS thermal performance evaluation for FHR

Q. Lv; Hsun Chia Lin; In Hun Kim; Xiaodong Sun; Richard N. Christensen; Thomas E. Blue; Graydon L. Yoder; Dane F Wilson; Piyush Sabharwall


2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016 | 2016

Relap5 model validation and benchmark for Dracs thermal performance

Hsun Chia Lin; Q. Lv; Shanbin Shi; Xiaodong Sun; Richard M. Christensen; Thomas E. Blue; Piyush Sabharwall


2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016 | 2016

Experimental study of Dracs steady-state and transient performance

Q. Lv; Hsun Chia Lin; Shanbin Shi; Xiaodong Sun; Richard M. Christensen; Thomas E. Blue; Graydon L. Yoder; Dane F Wilson; Piyush Sabharwall


Nuclear Engineering and Design | 2015

Scaling analysis for the direct reactor auxiliary cooling system for FHRs

Q. Lv; Xia Wang; In Hun Kim; Xiaodong Sun; Richard N. Christensen; Thomas E. Blue; Graydon L. Yoder; Dane F Wilson; Piyush Sabharwall


Transactions of the american nuclear society | 2012

Design of a scaled-down low-temperature DRACS test facility for an AHTR

Q. Lv; Xia Wang; I. Adams; Xiaodong Sun; Richard N. Christensen; Thomas E. Blue; Graydon L. Yoder; Dane F Wilson; Piyush Sabharwall


Transactions of the american nuclear society | 2011

Design of a scaled-down DRACS test facility for an AHTR

Xia Wang; Q. Lv; Xiaodong Sun; Richard N. Christensen; Thomas E. Blue; Graydon L. Yoder; Dane F Wilson; Piyush Sabharwall


Annals of Nuclear Energy | 2019

Phenomena identification and ranking table study for thermal hydraulics for Advanced High Temperature Reactor

Hsun-Chia Lin; Sheng Zhang; David J. Diamond; Stephen M. Bajorek; Richard M. Christensen; Yujun Guo; Graydon L. Yoder; Shanbin Shi; Q. Lv; Xiaodong Sun

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Graydon L. Yoder

Oak Ridge National Laboratory

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Dane F Wilson

Oak Ridge National Laboratory

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Xia Wang

Ohio State University

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