The Integral Test Facility Karlstein

被引:26
作者
Leyer, Stephan [1 ]
Wich, Michael [1 ]
机构
[1] AREVA NP GmbH Germany, Dept PTBD G, D-63067 Offenbach, Germany
关键词
D O I
10.1155/2012/439374
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 Integral Test Facility Karlstein (INKA) test facility was designed and erected to test the performance of the passive safety systems of KERENA, the new AREVA Boiling Water Reactor design. The experimental program included single component/system tests of the Emergency Condenser, the Containment Cooling Condenser and the Passive Core Flooding System. Integral system tests, including also the Passive Pressure Pulse Transmitter, will be performed to simulate transients and Loss of Coolant Accident scenarios at the test facility. The INKA test facility represents the KERENA Containment with a volume scaling of 1 : 24. Component heights and levels are in full scale. The reactor pressure vessel is simulated by the accumulator vessel of the large valve test facility of Karlstein-a vessel with a design pressure of 11MPa and a storage capacity of 125 m(3). The vessel is fed by a benson boiler with a maximum power supply of 22MW. The INKA multi compartment pressure suppression Containment meets the requirements of modern and existing BWR designs. As a result of the large power supply at the facility, INKA is capable of simulating various accident scenarios, including a full train of passive systems, starting with the initiating event-for example pipe rupture.
引用
收藏
页数:12
相关论文
共 19 条
[1]   Transition from depressurization to long term cooling in AP600 scaled integral test facilities [J].
Bessette, DE ;
di Marzo, M .
NUCLEAR ENGINEERING AND DESIGN, 1999, 188 (03) :331-344
[2]  
Bianconi G., 1992, WCAP13277
[3]  
Brosche, 1199 VGB POW TECH, V11
[4]  
Hamazaki R., 2009, P 13 INT TOP M NUCL
[5]  
Huggenberger M., 1998, P 6 INT C NUCL ENG I
[6]  
Huggenberger M., 1999, P 7 INT C NUCL ENG I
[7]  
Ishii M., 2005, P INT ATOM EN AG M I
[8]  
Kojima Y., 2010, INT C ADV NUCL POW P, P1135
[9]  
Lafi A. Y., 1999, P 9 INT TOP M NUCL R
[10]  
Leyer S., 2009, P ANN M NUCL TECHN D