PEMODELAN SISTEM PENDINGINAN SUNGKUP SECARA PASIF MENGGUNAKAN RELAP5
Keywords:
modeling, containment, AP1000, passiveAbstract
All advanced power reactors (Generation III+) utilize passive system to transfer heat by natural convection. One of the unique features of advanced power reactor of AP1000 is the presence of passive containment cooling system (PCS) designed to maintain containment pressure below its design pressure for 72 hours without operator intervention. During a design bases accident, such as loss of coolant accident or main steam line break, steam is released into the containment atmosphere and in contact with cooler steel containment vessel. Heat transfer from steam by convection of steam and conduction of steel wall will initiate air heating in the outside space of containment vessel and initiate natural convection of air from the bottom of air baffle due to the change in the air density. This paper is objected to get a containment model of AP1000 for showing the PCS function using RELAP5. Basic function to be focused is heat transfer phenomena from the steam to the wall containment and to the outside air to obtain natural convection of air. The methodology utilized are collecting design data, containment nodalization using RELAP5, and simulation of containment function based on certain design bases event condition. The results of simulation have shown the heat transfer phenomena from inside containment into the outside air by steam condensation and natural convection of the air. RELAP5 calculation of containment model shows an increase in containment pressure above the containment design pressure of 59 psig as compared in the AP1000 design document. That is because the recent RELAP5 modelling did not include the additional cooling of external surface of containment vessel from the the Passive Containment Cooling Water Storage Tank (PCCWST). The result of modeling will be used for further accident analyses of AP1000 involving the PCS function.
References
Jose N. Reyes. AP600 and AP1000 passive safety system design and testing in APEX. presented in IAEA-ICTP natural circulation training course; Trieste, Italy; 25-29 June 2007
T.L. Schulz. Westinghouse AP1000 advanced passive plant. Nuclear Engineering and Design . 2006; 236: 1547-1557.
https://doi.org/10.1016/j.nucengdes.2006.03.049
Andi Sofrany E, Surip Widodo, Susyadi, D.T. Sony Tjahjani, Hendro Tjahjono. Pengembangan Model untuk Simulasi Keselamatan Reaktor PWR 1000 MWe Generasi III+ menggunakan Program Komputer RELAP5. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega. 2011; 13, 1:50-62.
Andi Sofrany E, Surip Widodo, Susyadi, D.T. Sony Tjahjani, Hendro Tjahjono.Verifikasi kecelakaan hilangnya aliran air umpan pada reaktor daya PWR maju. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega. 2012; 14:2:76 - 90.
W.T. Sha, et al,. Analysis of large-scale test for AP-600 passive containment cooling system. Elsevier-Nuclear Engineering and Design; 2004
Westinghouse Electric Co. AP-1000 european design control document; Chapter 3: Reactor, EPS-GW-GL-700 Revision 0; 2009
Westinghouse Electric Co. AP-1000 european design control document, Chapter 6: Engineered Safety Features, EPS-GW-GL-700 Revision 0; 2009
Farzad Choobdar Rahim, et al,. Numerical modeling of LOCA accident in AP1000 reactor containment. Australian Journal of Basic and Applied Sciences. 2011 5(5): 482-495.
J. Yang, et al,. Simulation and analysis on 10-inch cold leg small break LOCA for AP1000. Annals of Nuclear Energy. 2012; 46: 81-89.
https://doi.org/10.1016/j.anucene.2012.03.007
Westinghouse Electric Co. AP1000 nuclear power plant: Coping with station blackout, Westinghouse Non-Proprietary Class 3; 2011.