NUMERICAL STUDY ON CONDENSATION IN IMMERSED CONTAINMENT SYSTEM OF ADVANCED SMR DURING UNCONTROLLED DEPRESSURIZATION

Authors

  • Susyadi Center for Nuclear Reactor Technology and Safety – PTKRN BATAN
  • Hendro Tjahjono Center for Nuclear Reactor Technology and Safety – PTKRN BATAN
  • D.T. Sony Tjahyani Center for Nuclear Reactor Technology and Safety – PTKRN BATAN

DOI:

https://doi.org/10.17146/tdm.2017.19.3.3680

Keywords:

Containment, Condensation, RELAP5, NuScale, Depresurization

Abstract

A number of Small Modular Reactor designs have been developed by several countries and mostly each comes with specific innovative improvements. One of them is NuScale reactor which implements a steel, small size immersed-in-pool containment system. This new approach derives new challenges as the control for temperature and pressure inside the containment is conducted without any active system. Passive heat transfer and condensation is important parameter that needs to be investigated for this kind of containment design. Hence, this work examines the condensation, pressure and the effect of pool temperature on the capability of the containment to remove heat and maintain integrity passively. The work is performed using numerical simulation by modeling the reactor into RELAP5 code. The calculation result shows that during depressurization, the maximum pressure limit of 5.5 MPa is not exceeded. Besides, the containment design provides enough capability to transfer heat from the containment to the water pool passively. This work also investigates sensitivity analysis of pool temperature which shows that for the increase of about 17 oC, the heat removal from the containment to water pool is only slightly affected with value less than 3 percent.

 

References

Ingersoll, D., et al., NuScale small modular reactor for Co-generation of electricity and water. Desalination, 2014. 340: p. 84-93.

https://doi.org/10.1016/j.desal.2014.02.023

Zhu, D., et al., Evaluation of in-vessel corium retention margin for small modular reactor ACP100. Annals of Nuclear Energy, 2016. 94: p. 684-690.

https://doi.org/10.1016/j.anucene.2016.04.015

Tashakor, S., E. Zarifi, and M. Naminazari, Neutronic simulation of CAREM-25 small modular reactor. Progress in Nuclear Energy, 2017. 99: p. 185-195.

https://doi.org/10.1016/j.pnucene.2017.05.016

Kim, Y.-S., et al., Application of direct passive residual heat removal system to the SMART reactor. Annals of Nuclear Energy, 2016. 89: p. 56-62.

https://doi.org/10.1016/j.anucene.2015.11.025

Dmitriev, S., et al., Computational and Experimental Investigations of the Coolant Flow in the Cassette Fissile Core of a KLT-40S Reactor. Journal of Engineering Physics and Thermophysics, 2017. 90(4): p. 941-950.

https://doi.org/10.1007/s10891-017-1641-7

Hidayatullah, H., S. Susyadi, and M.H. Subki, Design and technology development for small modular reactors-safety expectations, prospects and impediments of their deployment. Progress in Nuclear Energy, 2015. 79: p. 127-135.

https://doi.org/10.1016/j.pnucene.2014.11.010

Hou, X., Z. Sun, and W. Lei, Capability of RELAP5 code to simulate the thermalhydraulic characteristics of open natural circulation. Annals of Nuclear Energy, 2017. 109: p. 612-625.

https://doi.org/10.1016/j.anucene.2017.06.010

Wang, Y., Preliminary study for the passive containment cooling system analysis of the advanced PWR. Energy Procedia, 2013. 39: p. 240-247.

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

Hung, Z.-Y., et al., Analysis of AP1000 containment passive cooling system during a loss-of-coolant accident. Annals of Nuclear Energy, 2015. 85: p. 717-724.

https://doi.org/10.1016/j.anucene.2015.06.027

Tjahjono, H., Effect of Air Condition on AP-1000 Containment Cooling Performance in Station Black Out Accident. J. Tri Dasa Mega, 2015. 17(3).

https://doi.org/10.17146/tdm.2015.17.3.2323

Butt, H.N., et al., Assessment of passive safety system of a Small Modular Reactor (SMR). Annals of Nuclear Energy, 2016. 98: p. 191-199.

https://doi.org/10.1016/j.anucene.2016.07.018

Liu, Z. and J. Fan, Technology readiness assessment of small modular reactor (SMR) designs. Progress in Nuclear Energy, 2014. 70: p. 20-28.

https://doi.org/10.1016/j.pnucene.2013.07.005

NUSCALE, NuScale Final Safety Analysis Report (Rev. 0), in NuScale Standard Plant Design Certification Application 2016.

Kumar, M., A. Nayak, and J. Joshi, Investigations of natural convection and circulation in Passive Moderator Cooling System of an advanced reactor in a scaled test facility. Nuclear Engineering and Design, 2017. 322: p. 55-67.

https://doi.org/10.1016/j.nucengdes.2017.06.018

Tabadar, Z., et al., Thermal-hydraulic analysis of VVER-1000 residual heat removal system using RELAP5 code, an evaluation at the boundary of reactor repair mode. Alexandria Engineering Journal, 2017.

https://doi.org/10.1016/j.aej.2017.03.044

Khatry, J. and F. Aydogan, Design Basis Accident Analysis of a Small Modular Reactor. Journal of Thermal Engineering, 2017. 3(3): p. 1241-1258.

https://doi.org/10.18186/journal-of-thermal-engineering.323390

Susyadi, S., Thermal-Hydraulic Analysis of SMR With Naturally Circulating Primary System During Loss of Feed Water Accident. J. Tri Dasa Mega, 2016. 18(3): p. 117-126.

https://doi.org/10.17146/tdm.2016.18.3.2670

Susyadi, S., et al., Investigasi Karakteristik Termohidrolika Teras Reaktor Daya Kecil Dengan Pendinginan Sirkulasi Alam Menggunakan RELAP5. J. Tri Dasa Mega, 2016. 18(1).

https://doi.org/10.17146/tdm.2016.18.1.2330

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Published

2017-10-10

How to Cite

Susyadi, Tjahjono, H., & Tjahyani, D. S. (2017). NUMERICAL STUDY ON CONDENSATION IN IMMERSED CONTAINMENT SYSTEM OF ADVANCED SMR DURING UNCONTROLLED DEPRESSURIZATION. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, 19(3), 149–158. https://doi.org/10.17146/tdm.2017.19.3.3680