Influence analysis of natural ventilation system on radon concentration in Interim Storage for Radioactive Waste von Ratiko, R.

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Dynamic modeling and controlling of a spent nuclear fuel storage pool under periodic operation and station blackout conditions von Wahid, A., Sundari, T., Ratiko, R.

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Current and future strategies for spent nuclear fuel management in Indonesia von Ratiko, R., Wisnubroto, D.S., Nasruddin, N., Mahlia, T.M.I.

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Corrosion rate of SS 304 for liquid radioactive waste treatment facility von Heriyanto, Kuat, Purwanto, Yuli, Saputra, Dwi Luhur Ibnu, Setiawan, Risdiyana, Rachmadetin, Jaka, Aisyah, Aisyah, Artiani, Pungky Ayu, Ratiko, Ratiko

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Optimization of heat removal and radiation protection of dry cask storage for MTR spent nuclear fuel von Istavara, A., Ratiko, R., Aziz, M., Aisyah, A., Nasruddin, N.

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The Steps in Preventing, Monitoring and Removing of Fouling Scale on Operation of Evaporator von Salimin, Zainus, Kistriyani, Lilis, Ratiko

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Theoretical and Experimental Analysis on Influence of Natural Airflow on Spent Fuel Heat Removal in Dry Cask Storage von Ratiko, Ratiko, Sumarbagiono, Raden, Aisyah, Aisyah, Wati, Wati, Heriyanto, Kuat, Mirawaty, Mirawaty, Artiani, Pungky Ayu, Purwanto, Yuli, Saputra, Dwi Luhur Ibnu, Rachmadetin, Jaka, Setiawan, Risdiyana, Istavara, Arifin, Rauf, Abdullah Ahmad

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CRITICALITY SAFETY ANALYSIS OF THE DRY CASK DESIGN WITH AIR GAPS FOR RDNK SPENT PEBBLE FUELS STORAGECriticality Safety Analysis of the Dry Cask Design with Air Gaps for RDNK Spent... von Artiani, Pungky Ayu, Purwanto, Yuli, Aisyah, Aisyah, Ratiko, Ratiko, Rachmadetin, Jaka, Heriyanto, Kuat

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Quantification of the impact of temperature difference between two connected indoor spaces on 222Rn concentration von Ratiko, Moriizumi, J., Yamazawa, H., Nasruddin

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Effects of %FIMA on Storage-Safety Parameters of Spent Fuel from Experimental Pebble-Bed Reactor von Aisyah, Aisyah, Mirawaty, Mirawaty, Saputra, Dwi Luhur Ibnu, Setiawan, Risdiyana, Artian, Pungky Ayu, Ratiko, Ratiko, Nasruddin, Nasruddin

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Radionuclide characterization and handling strategy of irradiated Fission Product Material (FPM) capsule waste from molybdenum-99 production von Aisyah, Artiani, P. A., Rachmadetin, J., Parjono, Saputra, D. L. I., Setiawan, R., Heriyanto, K., Ratiko, Wati, Purwanto, Y., Nurliati, G., Mirawaty

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Radioactive Fission Waste of The Conversion of High-Enriched Uranium to Low-Enriched Uranium Target on 99Mo Production von Aisyah, Hendro, Parjono, Ibnu S, D L, Setiawan, R, Artiani, P A, Rachmadetin, J, Heriyanto, K, Ratiko, Nurliati, G, Mirawaty, Wati

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Radioactive Fission Waste of The Conversion of High-Enriched Uranium to Low-Enriched Uranium Target on 99 Mo Production von Aisyah, Hendro, Parjono, Ibnu S, D L, Setiawan, R, Artiani, P A, Rachmadetin, J, Heriyanto, K, Ratiko, Nurliati, G, Mirawaty, Wati

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PEMODELAN DINAMIK PENDINGINAN BAHAN BAKAR NUKLIR BEKAS REAKTOR RISET SECARA NATURAL KONVEKSI PADA PROTOTIPE DRY CASK STORAGE von Istavara, Arifin, Ratiko, Ratiko, Pratama, Hendra Adhi, Nasruddin, Nasruddin

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Neutron shielding performance of Cd/316L composite fabricated by arc plasma sintering von Heriyanto, Kuat, Rachmadetin, Jaka, Sudjadi, Usman, Dimyati, Arbi, Salam, Rohmad, Aisyah, Artiani, Pungky Ayu, Ratiko, Ramadhani, Achmad, Ajiriyanto, Maman Kartaman, Kriswarini, Rosika, Sukaryo, Sulistioso Giat, Prajitno, Djoko Hadi, Rivai, Abu Khalid, Setyawan, Daddy

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