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Featured researches published by Shanbin Shi.


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.


Annals of Nuclear Energy | 2016

Experimental and numerical study of a printed circuit heat exchanger

M. Chen; Xiaodong Sun; Richard N. Christensen; Shanbin Shi; Isaac Skavdahl; Vivek Utgikar; Piyush Sabharwall


Annals of Nuclear Energy | 2017

Modeling of flashing-induced flow instabilities for a natural circulation driven novel modular reactor

Shanbin Shi; Mamoru Ishii


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


2016 24th International Conference on Nuclear Engineering | 2016

Scaling Analysis and Facility Design for Stability Investigation During Accidents in a PWR-Type SMR

Yikuan Yan; Shanbin Shi; Mamoru Ishii


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


Nuclear Engineering and Design | 2018

Thermal hydraulic performance analysis of a post-CHF heat transfer test facility

Qingqing Liu; Shanbin Shi; Xiaodong Sun; Joseph M. Kelly


Annals of Nuclear Energy | 2018

Mass transport analysis for tritium removal in FHRs

Xiao Wu; Shanbin Shi; Sheng Zhang; David J. Arcilesi; Richard M. Christensen; Piyush Sabharwall; Xiaodong Sun


Annals of Nuclear Energy | 2018

Code validation of a scaled-down DRACS model in RELAP5/SCDAPSIM/MOD 4.0

Hsun-Chia Lin; Q. Lv; Shanbin Shi; Xiaodong Sun; Richard M. Christensen; Graydon L. Yoder

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Graydon L. Yoder

Oak Ridge National Laboratory

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Q. Lv

Ohio State University

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Xiao Wu

Ohio State University

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