Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor

被引：1
|
作者：
Maraczy, Csaba [1 ]
Hegyi, Gyorgy [1 ]
Trosztel, Istvn [1 ]
Temesvari, Emese [1 ]
机构：
[1] Hungarian Acad Sci, Energy Res Ctr, POB 49, H-1525 Budapest 114, Hungary
来源：
JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE | 2016年 / 2卷 / 01期
关键词：
fuel qualification test; supercritical water; research reactor; control rod withdrawal; coupled neutronic-thermohydraulic analysis;
D O I：
10.1115/1.4030933
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 aim of the supercritical water reactor-fuel qualification test (SCWR-FQT) Euratom-China collaborative project is to design an experimental facility for qualification of fuel for the supercritical water-cooled reactor. The facility is intended to be operated in the LVR-15 research reactor in the Czech Republic. The pressure tube of the FQT facility encloses four fuel rods that will operate in similar conditions to the evaporator of the HPLWR reactor. This article deals with the three-dimensional (3D) coupled neutronic-thermohydraulic steady-state and transient analysis of LVR-15 with the fueled loop. Conservatively calculated enveloping parameters (e.g., reactivity coefficients) were determined for the safety analysis. The control rod withdrawal analysis of the FQT facility with and without reactor SCRAM was carried out with the KIKO3D-ATHLET-coupled dynamic code.
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页数：5
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