INVESTIGASI TRANSIEN TEKANAN DAN TEMPERATUR SUNGKUP AP1000 DALAM KECELAKAAN SBO DENGAN SET-POINT TEKANAN PENGGUYURAN BERBEDA

Authors

  • Hendro Tjahjono Pusat Teknologi dan Keselamatan Reaktor Nuklir, BATAN

DOI:

https://doi.org/10.17146/tdm.2015.17.1.2233

Keywords:

Transient pressure, containment external cooling set-point, AP1000, SBO

Abstract

AP1000 reactor applying external cooling concept to anticipate the increase in pressure due to Station Black Out (SBO). Disposal mechanism of decay heat conducted through the Passive Residual Heat Removal System (PRHRS) to In-containment Refueling Water Storage Tank (IRWST) and subsequently forwarded to the reactor containment. Containment is externally cooled through natural convection in the air gap and through evaporation cooling water poured on the outer surface of the containment wall when the pressure attaints 1.7 bars according to the applied pressure set-point. With this mechanism, the pressure will increase until it reaches certain maximum value and then decrease when containment cooling already begun effectively. The purpose of this study was to determine the effect of the set-point to the maximum pressure and temperature reached. The utilized method is to perform simulations using Matlab-07 model of analytical calculations based on a transient state that is capable of estimating the power of heat evacuated and the pressure in the containment. The simulation results show the pattern of pressure and temperature transient rises to a maximum and drops back to a value that is relatively constant. With the set-point variation ranging from 1.7 bars to 5 bars, the maximum pressure varies from 3.5 bars to 5 bars and the maximum temperature varies from 117 °C to 125 °C. It can be concluded that with increasing the set-point pressure of starting the external cooling with water, the maximum pressure and temperature increase.

 

References

Jun Wang, Wenxi Tian, Yapei Zhang, Lie Chen, Longze Li, Luteng Zhang, Yukun Zhou, Guanghui Su, Suizheng Qiu. The Development of Module In-Vessel Degraded Severe Accident Analysis Code MIDAC and the Relevant Research for CPR1000 during the Station Blackout Scenario. Progress in Nuclear Energy 76 (2014) 44-54.

https://doi.org/10.1016/j.pnucene.2014.05.015

Soon Heung Chang, Sang Ho Kim, Jae Young Choi. Design of Integrated Passive Safety System (IPSS) for ultimate passive safety of nuclear power plants. Nuclear Engineering and Design 260 (2013) 104-120.

https://doi.org/10.1016/j.nucengdes.2013.03.018

Westinghouse Non-Proprietary Class 3. Westinghouse AP1000 Nuclear Power Plant Coping with Station Blackout, April 2011.

YE Cheng, ZHENG Mingguang, WANG Yong, QIU Zhongming. Study on the Long-Term Passive Cooling Extension of AP1000 Reactor. Nuclear Science and Techniques 24 (2013) 040601.

Mukesh Kumar, A K Nayak, V Jain, P K Vijayan, And K K Vaze. Managing a Prolonged Station Blackout Condition in AHWR by Passive Means. Nuclear Engineering and Technology, Vol. 45 No. 5 October 2013.

https://doi.org/10.5516/NET.02.2012.086

Andrija Volkanovski, Andrej Proˇsek. Extension of Station Blackout Coping Capability and Implications on Nuclear Safety. Nuclear Engineering and Design 255 (2013) 16- 27.

https://doi.org/10.1016/j.nucengdes.2012.09.031

Hendro Tjahjono. Optimasi Pendinginan Eksternal pada Model Sungkup PWR-1000 menggunakan Metode Estimasi Analitik. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, Volume 16, Nomor 2, Juni 2014.

Hendro Tjahjono. Analisis Transien Parameter Termal Droplet dalam Menara Pendingin PLTN. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, Vol.11 No. 03, Oktober 2009.

Wang Yan. Analysis Model for the Passive Containment Cooling System, Journal of Convergence Information Technology(JCIT) Volume 7, Number 13, July 2012.

https://doi.org/10.4156/jcit.vol7.issue13.9

Wang Yan. Preliminary Study for the Passive Containment Cooling Analysis of the Advanced PWR, Energy Procedia 39 ( 2013 ) 240 - 247.

https://doi.org/10.1016/j.egypro.2013.07.210

Farzad Choobdar Rahim. Analysis of Containment Volume Effect on the Pressure and Temperature during LOCA in the AP1000 Reactor Containment, IJNESE Volume 2, Issue 3 September 2012, pp. 92-96.

Andi Sofrany Ekariansyah, Susyadi, Surip Widodo. Pemodelan Sistem Pendinginan Sungkup secara Pasif menggunakan RELAP5. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, Vol. 14 No.3 Oktober 2012, pp. 137-145.

M. Ragheb. Decay Heat Generation in Fission Reactors. www.ewp.rpi.edu, Univercity of Illinois, Ragheb-Ch8-2011.

Yu Yu, Fenglei Niu, Shengfei Wang, Yingqiu Hu. One-Dimensional Model For Containment In AP1000 Nuclear Power Plant Based on Thermal Stratification. Applied Thermal Engineering 70 (2014) 25-32.

https://doi.org/10.1016/j.applthermaleng.2014.04.070

Westinghouse Electric Co. AP1000 European Design Control Document, Chapter 6: Engineered Safety Features. EPS-GW-GL-700 Revision 0, 2009.

Downloads

Published

2015-08-09

How to Cite

Tjahjono, H. (2015). INVESTIGASI TRANSIEN TEKANAN DAN TEMPERATUR SUNGKUP AP1000 DALAM KECELAKAAN SBO DENGAN SET-POINT TEKANAN PENGGUYURAN BERBEDA. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, 17(1), 1–12. https://doi.org/10.17146/tdm.2015.17.1.2233