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

被引:8
|
作者
Lin, Hsun-Chia [1 ,2 ]
Zhang, Sheng [1 ,2 ]
Diamond, David [3 ]
Bajorek, Stephen [4 ]
Christensen, Richard [1 ,5 ]
Guo, Yujun [6 ]
Yoder, Graydon [7 ]
Shi, Shanbin [1 ,2 ]
Lv, Qiuping [1 ,8 ]
Sun, Xiaodong [1 ,2 ]
机构
[1] Ohio State Univ, Dept Mech & Aerosp Engn, Nucl Engn Program, 201 W 19th Ave, Columbus, OH 43210 USA
[2] Univ Michigan, Dept Nucl Engn & Radiol Sci, 2355 Bonisteel Blvd, Ann Arbor, MI 48109 USA
[3] Brookhaven Natl Lab, 33 N Renaissance Rd, Upton, NY 11973 USA
[4] US Nucl Regulatory Commiss, Washington, DC 20555 USA
[5] Univ Idaho, Nucl Engn Program, 1776 Sci Ctr Dr, Idaho Falls, ID 83402 USA
[6] Canadian Nucl Safety Commiss, 280 Slater St, Ottawa, ON K1P 5S9, Canada
[7] Oak Ridge Natl Lab, 1 Bethel Valley Rd, Oak Ridge, TN 37830 USA
[8] Argonne Natl Lab, 9700 Cass Ave, Lemont, IL 60439 USA
关键词
AHTR; FHR; PIRT; Thermal hydraulics;
D O I
10.1016/j.anucene.2018.08.038
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 Advanced High Temperature Reactor (AHTR) is a conceptual design of a Fluoride salt-cooled High temperature Reactor (FHR) utilizing (LiF)-Li-7-BeF2 (66-34 mol%) as its primary coolant. To identify key phenomena that impose potential challenges on thermal hydraulics modeling and simulation of such a reactor system, a thermal hydraulics phenomena identification and ranking table (TH-PIRT) study was performed for the AHTR in a Department of Energy Nuclear Energy University Program (NEUP) integrated research project led by Georgia Institute of Technology. A panel of experts from regulators, industries, national laboratories, and academia was assembled for the study. In this paper, the TH-PIRT5 identified by the panel for two events, namely, station blackout and simultaneous withdrawal of all control rods, are summarized and discussed in detail. In addition, the key phenomena that warrant further study and research for AHTR analysis are identified to support the validation of thermal hydraulics system-level analysis codes and computational fluid dynamics simulation tools, as well as future FHR reactor licensing. Crown Copyright (C) 2018 Published by Elsevier Ltd. All rights reserved.
引用
收藏
页码:257 / 269
页数:13
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