• Vol 9, No 1 (2018)
  • Mechanical Engineering

Optimization of Dry Storage for Spent Fuel from G.A. Siwabessy Nuclear Research Reactor

Ratiko Ratiko, Shandy Arysenna Samudera, Richiditya Hindami, Amudi Tua Siahaan, Leo Naldi, Dian Hapsari Safitri, T. M. I. Mahlia, Nasruddin Nasruddin


Publish at : 27 Jan 2018 - 08:51
IJtech : IJtech Vol 9, No 1 (2018)
DOI : https://doi.org/10.14716/ijtech.v9i1.775

Cite this article as:
Ratiko, R., Samudera, S.A., Hindami, R., Siahaan, A.T., Naldi, L., Safitri, D.H., Mahlia, T.M.I., Nasruddin, N., 2018. Optimization of Dry Storage for Spent Fuel from G.A. Siwabessy Nuclear Research Reactor. International Journal of Technology. Volume 9(1), pp.55-67
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Ratiko Ratiko Radioactive Waste Technology Center, National Nuclear Energy Agency of Indonesia (BATAN), Serpong, Indonesia
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Shandy Arysenna Samudera Department of Mechanical Engineering, Universitas Indonesia, 16424 Depok, Indonesia
Richiditya Hindami Department of Mechanical Engineering, Universitas Indonesia, 16424 Depok, Indonesia
Amudi Tua Siahaan Department of Mechanical Engineering, Universitas Indonesia, 16424 Depok, Indonesia
Leo Naldi Department of Mechanical Engineering, Universitas Indonesia, 16424 Depok, Indonesia
Dian Hapsari Safitri Department of Mechanical Engineering, Universitas Indonesia, 16424 Depok, Indonesia
T. M. I. Mahlia Department of Mechanical Engineering, Universiti Tenaga Nasional, 43009 Kajang, Selangor, Malaysia
Nasruddin Nasruddin Department of Mechanical Engineering, Universitas Indonesia, 16424 Depok, Indonesia
Email to Corresponding Author

Abstract
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This study proposes a method of optimizing the dry storage design for nuclear-spent fuel from the G.A. Siwabessy research reactor at National Nuclear Energy Agency of Indonesia (BATAN). After several years in a spent fuel pool storage (wet storage), nuclear spent fuel is often moved to dry storage. Some advantages of dry storage compared with wet storage are that there is no generation of liquid waste, no need for a complex and expensive purification system, less corrosion concerns and that dry storage is easier to transport if in the future the storage needs to be sent to the another repository or to the final disposal. In both wet and dry storage, the decay heat of spent fuel must be cooled to a safe temperature to prevent cracking of the spent fuel cladding from where hazardous radioactive nuclides could be released and harm humans and the environment. Three optimization scenarios including the thermal safety single-objective, the economic single-objective and the multi-objective optimizations are obtained. The optimum values of temperature and cost for three optimization scenarios are 317.8K (44.7°C) and 11638.1 US$ for the optimized single-objective thermal safety method, 337.1K (64.0°C) and 6345.2 US$ for the optimized single-objective cost method and 325.1K (52.0°C) and 8037.4 US$ for the optimized multi-objective method, respectively.

Decay heat; Dry storage; Multi-objective optimization; Spent fuel

Conclusion

Based on the optimization results, the spent fuel from BATAN can be transferred from wet storage to the dry storage designed in this study after 4 years of storage. In addition, this report shows that the passive cooling system in the dry storage that uses a stack effect can decrease the temperature to safe parameters.

The optimum values of temperature and cost at the single-objective thermal safety optimization are 317.8K (44.7°C) and 11638.1 US$, whereas the optimum values at the single-objective cost optimization are 337.1K (64.0°C) and 6345.2 US$. Using multi-objective optimization, the optimum values of temperature and cost are 325.1K (52.0°C) and 8037.4 US$, respectively.


References

Andrianov, AA, Kuptsov, IS, & Utyanskaya, TV. (2016). Application of multi-objective and robust optimization methods for a comparative evaluation of nuclear energy system deployment scenarios. Nuclear Energy and Technology, 2(2Andrianov, A.A., Kuptsov, I.S., Utyanskaya, T.V., 2016. Application of Multi-objective and Robust Optimization Methods for a Comparative Evaluation of Nuclear Energy System Deployment Scenarios. Nuclear Energy and Technology, Volume 2(2), pp. 102–107

Apostolov, T., Manolova, M., Prodanova, R., 2001. Criticality Calculations of Various Spent Fuel Casks-possibilities for Burn Up Credit Implementation. In: International Meeting 'Nuclear Power in Eastern Europe: Safety, European Integration, Free Electricity Market' and the Tenth Anniversary of Bulgarian Nuclear Society, Bulgaria, Volume 32(47)

Artiani, P.A., Mirawaty, Heriyanto, K., 2017. Analysis of Criticality for Spent Fuel of RSG Gas Reactor in Aluminium Storage Rack. Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir (Urania Journal of Scientific Nuclear Fuel Cycle), Volume 23(2), pp. 127–137

BATAN, 2009. Safety Analysis Report - Interim Storage for Spent Fuel.

BATAN-IAEA, 1992. Engineering Contract: Transfer Channel and ISSF for BATAN, Preliminary Design Package. November

Botsch, W., Smalian, S., Hinterding, P., Voelzke, H., Wolff, D., Kasparek, E., 2013. Safety Aspects of Dry Spent Fuel Storage and Spent Fuel Management. In: WM2013: Waste Management Conference: International Collaboration and Continuous Improvement, United States, Volume 45(17), pp. 24–28

Ji, J., Li, M., Shi, M., Shi, W., Gao, Z., Sun, J., Lo, S., 2017. Deflection Characteristic of Flame with the Airflow Induced by Stack Effect. International Journal of Thermal Sciences, Volume 115, pp. 160–168

Lee, C.M., Lee, K.J., 2007. A Study on Operation Time Periods of Spent Fuel Interim Storage Facilities in South Korea. Progress in Nuclear Energy, Volume 49(4), pp. 323–333

Lee, D-G. Sung, N-H., Park, J-H., Chung, S-H., 2016. An Assessment of Temperature History on Concrete Silo Dry Storage System for CANDU Spent Fuel. Annals of Nuclear Energy, Volume 94, pp. 263–271

Ratiko, 2012. Multi-objective Optimization of Air Conditioning System for Interim Vault Dry Storage. Journal of Waste Management Technology, Volume 13(2), pp. 39–50

Sakamoto, K., Koga, T., Wataru, M., Hattori, Y., 2000. Heat Removal Characteristics of Vault Storage System with Cross Flow for Spent Fuel. Nuclear Engineering and Design, Volume 195(1), pp. 57–68

Simmonds, P., Zhu, R., 2013. Stack Effect Guidelines for Tall, Mega Tall and Super Tall Buildings. International Journal of High-Rise Buildings, Volume 2(4), pp. 323–330

Standards, IAEA Safety, 2014. Criticality Safety in the Handling of Fissile Material. Vienna

Yun, M., Christian, R., Kim, B.G., Almomani, B., Ham, J., Lee, S., Kang, H.G., 2017. A Software Tool for Integrated Risk Assessment of Spent Fuel Transportation and Storage. Nuclear Engineering and Technology, Volume 49(4), pp. 721–733

 ), 102-107.

Apostolov, T, Manolova, M, & Prodanova, R. (2001). Criticality calculations of various spent fuel casks-possibilities for burn up credit implementation.

Artiani, Pungky Ayu, Mirawaty, Mirawaty, & Heriyanto, Kuat. (2017). ANALYSIS OF CRITICALITY FOR SPENT FUEL OF RSG-GAS REACTOR IN ALUMINIUM STORAGE RACK. Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir, 23(2).

. BATAN – IAEA ENGINEERING CONTRACT, “Transfer Channel and ISSF for BATAN, Preliminary Design Package”. (November 1992). BATAN. (2009). Safety Analysis Report - Interim Storage for Spent Fuel.

Botsch, Wolfgang, Smalian, Silva, Hinterding, Peter, Völzke, Holger, Wolff, Dietmar, & Kasparek, Eva-Maria. (2013). Safety aspects of dry spent fuel storage and spent fuel management. Paper presented at the Proc. Waste Management Symp.

Ji, Jie, Li, Man, Shi, Wenxi, Gao, Zihe, Sun, Jinhua, & Lo, Siuming. (2017). Deflection characteristic of flame with the airflow induced by stack effect. International Journal of Thermal Sciences, 115, 160-168.

Lee, Chang Min, & Lee, KunJai. (2007). A study on operation time periods of spent fuel interim storage facilities in South Korea. Progress in Nuclear Energy, 49(4), 323-333.

Lee, Dong-Gyu, Sung, Nak-Hoon, Park, Jea-Ho, & Chung, Sung-Hwan. (2016). An assessment of temperature history on concrete silo dry storage system for CANDU spent fuel. Annals of Nuclear Energy, 94(Supplement C), 263-271. doi: https://doi.org/10.1016/j.anucene.2016.03.007

Ratiko. (2012). Multi-Objective Optimization of Air Conditioning System for Interim Vault Dry Storage. Journal of Waste Management Technology, 13(2), 39-50.

Sakamoto, Kazuaki, Koga, Tomonari, Wataru, Masumi, & Hattori, Yasuo. (2000). Heat removal characteristics of vault storage system with cross flow for spent fuel. Nuclear Engineering and Design, 195(1), 57-68. doi: https://doi.org/10.1016/S0029-5493(99)00177-6

Simmonds, Peter, & Zhu, Rui. (2013). Stack Effect Guidelines for Tall, Mega Tall and Super Tall Buildings. International Journal of High-Rise Buildings, 2(4).

Standards, IAEA Safety. (2014). Criticality Safety in the Handling of Fissile Material. Vienna.

Yun, Mirae, Christian, Robby, Kim, Bo Gyung, Almomani, Belal, Ham, Jaehyun, Lee, Sanghoon, & Kang, Hyun Gook. (2017). A software tool for integrated risk assessment of spent fuel transportation and storage. Nuclear Engineering and Technology.