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

被引:6
|
作者
Lv, Q. [1 ,4 ]
Lin, H. C. [1 ]
Shi, S. [1 ]
Sun, X. [1 ]
Christensen, R. N. [1 ]
Blue, T. E. [1 ]
Yoder, G. [2 ]
Wilson, D. [2 ]
Sabharwall, P. [3 ]
机构
[1] Ohio State Univ, Dept Mech & Aerosp Engn, Nucl Engn Program, 201 W 19th Ave, Columbus, OH 43210 USA
[2] Oak Ridge Natl Lab, POB 2008, Oak Ridge, TN 37831 USA
[3] Idaho Natl Lab, 2525 Fremont Ave, Idaho Falls, ID 83415 USA
[4] Argonne Natl Lab, 9700 Cass Ave, Lemont, IL 60439 USA
关键词
FHR; DRACS; decay heat removal; REACTOR;
D O I
10.13182/NT16-41
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
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.
引用
收藏
页码:319 / 337
页数:19
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