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No.
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Judul
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Sumber Dana
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Keterangan
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1.
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Heat Transfer Problems Verification of Finite Volume Particle (FVP) Method-based Code
(Rida SN Mahmudah, Denny Darmawan, Koji Morita)
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MIPA
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Dipresentasikan pada: The 3rd International Conference on Research, Implementation and Education of Mathematics and Science, UNY, 16-17 Mei 2016
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2.
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Preliminary Study of Lead-oxide Cooled Fast Reactor with Natural Uranium As An Input Fuel with Reactor Shuffling Strategy
(Rida SN Mahmudah, Zaki Su’ud)
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-
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Dipresentasikan pada: The 5th International Conference on Advanced in Nuclear Sciences and Engineering, ITB, 18-20 November 2015
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3.
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3D Simulations of Solid-melt Mixture Flow with Melt Solidification Using a Finite Volume Particle Method
(Rida SN Mahmudah, M. Kumabe, T. Suzuki, L. Guo, K. Morita)
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MEXT Japan
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Journal of Nuclear Science and Technology, Vol. 48, No.10 (2011) pp 1327-1336
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4.
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Particle-based Simulations of Molten Metal Flows with Solidification
(Rida SN Mahmudah, M. Kumabe, T. Suzuki, L. Guo, K. Morita)
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MEXT Japan
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Memoirs of the Faculty of Engineering, Kyushu University,Vol.71, No.1 (2011) pp. 17-29
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5.
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Numerical Simulation of Effective Viscosity in Solid-Fluid Mixture Flows Using Finite Volume Particle Method
(T. Suzuki, L. Guo, Rida SN Mahmudah, K. Morita)
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MEXT Japan
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Dipresentasikan pada:
19th International Conference on Nuclear Engineering (ICONE-19), Chiba, Japan, 24-25 Oktober 2011
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6.
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3D Simulation of Solid-melt Mixture Flow with Phase Change Using Finite Volume Particle Method
(Rida SN Mahmudah, M. Kumabe, W. Torii, I. Miya, T. Takeda, T. Suzuki, L. Guo, K. Morita)
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MEXT Japan
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Dipresentasikan pada:
7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), Chuncheon, Korea, Nov. 14-17, 2010
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7.
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3D Simulation of Molten Metal Freezing Behavior Using Finite Volume Particle Method
(Rida SN Mahmudah, M. Kumabe, T. Suzuki, L. Guo, K. Morita, K. Fukuda)
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MEXT Japan
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Dipresentasikan pada:
18th International Conference on Nuclear Engineering (ICONE-18), Xi'an, China, May 17-21, 2010
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8.
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Fission Yield Calculation Method and its Effect in Nuclear Fuel Cell Homogenization Calculation
(Zaki Suud, M. Ali Safii, Rida SNM)
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Indonesian Journal of Physics, Vol. 20, No. 1(2009) pp. 33-36
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9.
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Feasibility Design Study of Long Life BWR with Natural Uranium/Thorium as Fuel Cycle Input
(Zaki Suud, Rizal Kurniadi, Rida SNM, Zuhair)
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Indonesian Journal of Physics, Vol. 20, No. 1(2009) pp. 17-20
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10.
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The Fission Products (FP) Group Constant Treatment For Long Life Pb-Bi Cooled Fast Power Reactors
(Zaki Suud, A. Waris, Rida SNM)
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Int. Journal of Energy Science and Technology (IJNEST), Vol. 4 no. 3 (2009) pp.201-216
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11.
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Design Study of Pb-Bi Cooled Fast Reactors Which Fuel Cycle Input is Natural Uranium
(Rida SNM and Zaki Suud)
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Int. Journal of Energy Science and Technology (IJNEST), Vol. 4 no. 3 (2009) pp. 217-222
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12.
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The Utilization of Thorium for Long Life Small Thermal Reactors Without On-Site Refueling
(Iyos Subki, Asril P, Rida SNM, Zaki S, Eka SR, Muh. Nurul S., Topan, Yuli A., Sedyartomo S)
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Progress of Nuclear Energy, Vol. 50 (2008), p. 152-156
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13.
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Design Study of Long Life Pb-Bi Cooled Reactors With natural Uranium as Fuel Cycle Input Using Radial Fuel Shuffling Strategy
(Rida SNM and Zaki S)
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-
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Dipresentasikan pada:
International Conference on Nuclear Science and Engineering (ICANSE-1), Bandung, Indonesia, Nov 14-16, 2007
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14
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The Utilization of Thorium for Long Life Small Thermal Reactors Without On-Site Refueling
(Iyos Subki, Asril Pramutadi, Rida SNM, Zaki Su’ud, Eka Sapta R, Muh. Nurul S. Topan S, Yuli Astuti, Sedyartomo Soentono)
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Mandiri
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Dipresentasikan pada:
2nd COE INES International Symposium, Yokohama, Japan, Dec. 27 – 31, 2006
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