Dr. Rida Siti Nur'aini Mahmudah, S.Si., M.Si.

Status : Dosen

Dr. Rida Siti Nur'aini Mahmudah, S.Si., M.Si. on Google Scholar

Identitas
NIP : 198408182014042001
Jenis Kelamin : Perempuan
Agama : Islam
Keahlian :

Fisika Reaktor Nuklir

Computational Fluid Dynamics


Riwayat Pendidikan :

Program

S1

S2

S3

Nama Perguruan Tinggi

Institut Teknologi Bandung

Institut Teknologi Bandung

Kyushu University

Bidang Ilmu

Fisika

Fisika

Department Applied Quantum Physics and Nuclear Engineering

Tahun Masuk

2002

2006

2008

Tahun Lulus

2006

2008

2011

Judul Skripsi/Tesis/ Disertasi

Desain Studi Reaktor Cepat Berpendingin Pb-Bi dengan Uranium Alam sebagai Input dalam Operasinya

Desain Studi Reaktor Cepat Berpendingin Pb-Bi Dengan Strategi Shuffling Menggunakan Uranium Alam

Development of Particle-based Simulation Methods for Multiphase Flows with Solidification

Nama Pembimbing

Prof. Zaki Su’ud

Prof. Zaki Su’ud

Prof. Koji Morita

 

Unit Kerja
Fakultas MIPA
Jurusan :
Pendidikan Fisika
Golongan :
III/b
Jabatan :
Asisten Ahli
Contact
email : rida@uny.ac.id
Blog :
Facebook :
Bidang Pendidikan

No.

Matakuliah

Semester/Tahun

Strata

Prodi

1.

Electricity and Magnetism Instruments

Genap 2014/2015

S1

Pend.Fisika

2.

Sensor dan Transduser

Gasal 2015/2016

S1

Pend. Fisika

3.

Fisika Inti Lanjut

Gasal 2015/2016

S1

Fisika

4.

Analisis Numerik

Genap 2015/2016

S1

Fisika

5.

Praktikum Analisis Numerik

Genap 2015/2016

S1

Fisika

6.

Fisika Inti

Genap 2015/2016

S1

Pend. Fisika

7.

Praktikum Fisika Inti

Genap 2015/2016

S1

Pend. Fisika

8.

English for Physics 1

Gasal 2016/2017

S1

Pend. Fisika dan Fisika

9.

Fisika Inti Lanjut

Gasal 2016/2017

S1

Fisika

10.

Analisis Numerik

Genap 2016/2017

S1

Fisika

11.

Praktikum Analisis Numerik

Genap 2016/2017

S1

Fisika

12.

Reaksi Nuklir dan Data Nuklir

Genap 2016/2017

S1

Fisika

13.

English for Physics 2

Genap 2016/2017

S1

Pend. Fisika

 

File Bidang Pendidikan :
rps-analisis-numerik
materi-1-akar-persamaan
materi-2-sistem-persamaan-linier-1
materi-3-sistem-persamaan-linier-2
materi-4-diferensiasi-numerik
rps-fisika-inti
materi-1-pendahuluan
materi-2-struktur-inti-atom
materi-3-radioaktivitas
Bidang Penelitian

No.

Judul

Sumber Dana

Keterangan

1.

Heat Transfer Problems Verification of Finite Volume Particle (FVP) Method-based Code

(Rida SN Mahmudah, Denny Darmawan, Koji Morita)

MIPA

Dipresentasikan pada: The 3rd International Conference on Research, Implementation and Education of Mathematics and Science, UNY, 16-17 Mei 2016

2.

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)

-

Dipresentasikan pada: The 5th International Conference on Advanced in Nuclear Sciences and Engineering, ITB, 18-20 November 2015

3.

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)

MEXT Japan

Journal of Nuclear Science and Technology, Vol. 48, No.10 (2011) pp 1327-1336

4.

Particle-based Simulations of Molten Metal Flows with Solidification

(Rida SN Mahmudah, M. Kumabe, T. Suzuki, L. Guo, K. Morita)

MEXT Japan

Memoirs of the Faculty of Engineering, Kyushu University,Vol.71, No.1 (2011) pp. 17-29

5.

Numerical Simulation of Effective Viscosity in Solid-Fluid Mixture Flows Using Finite Volume Particle Method

(T. Suzuki, L. Guo, Rida SN Mahmudah, K. Morita)

MEXT Japan

Dipresentasikan pada:

19th International Conference on Nuclear Engineering (ICONE-19), Chiba, Japan, 24-25 Oktober 2011

6.

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)

MEXT Japan

Dipresentasikan pada:

7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), Chuncheon, Korea, Nov. 14-17, 2010

7.

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)

MEXT Japan

Dipresentasikan pada:

18th International Conference on Nuclear Engineering (ICONE-18), Xi'an, China, May 17-21, 2010

8.

Fission Yield Calculation Method and its Effect in Nuclear Fuel Cell Homogenization Calculation

(Zaki Suud, M. Ali Safii, Rida SNM)

 

Indonesian Journal of Physics, Vol. 20, No. 1(2009) pp. 33-36

9.

Feasibility Design Study of Long Life BWR with Natural Uranium/Thorium as Fuel Cycle Input

(Zaki Suud, Rizal Kurniadi, Rida SNM, Zuhair)

 

Indonesian Journal of Physics, Vol. 20, No. 1(2009) pp. 17-20

10.

The Fission Products (FP) Group Constant Treatment For Long Life Pb-Bi Cooled Fast Power Reactors

(Zaki Suud, A. Waris, Rida SNM)

 

Int. Journal of Energy Science and Technology (IJNEST), Vol. 4 no. 3 (2009) pp.201-216

11.

Design Study of Pb-Bi Cooled Fast Reactors Which Fuel Cycle Input is Natural Uranium

(Rida SNM and Zaki Suud)

 

Int. Journal of Energy Science and Technology (IJNEST), Vol. 4 no. 3 (2009) pp. 217-222

12.

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)

 

Progress of Nuclear Energy, Vol. 50 (2008), p. 152-156

13.

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)

-

Dipresentasikan pada:

International Conference on Nuclear Science and Engineering (ICANSE-1), Bandung, Indonesia, Nov 14-16, 2007

14

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)

Mandiri

Dipresentasikan pada:

2nd COE INES International Symposium, Yokohama, Japan, Dec. 27 – 31, 2006

 

 

File Bidang Penelitian :
utilization-thorium-long-life-small-thermal-reactors-without-site-refueling
design-study-long-life-pb-bi-cooled-reactors-natural-uranium-fuel-cycle-input-using-radial-fuel-shuf
design-study-pb-bi-cooled-fast-reactors-which-fuel-cycle-input-natural-uranium
fission-products-fp-group-constant-treatment-long-life-pb-bi-cooled-fast-power-reactors
feasibility-design-study-long-life-bwr-natural-uraniumthorium-fuel-cycle-input
fission-yield-calculation-method-and-its-effect-nuclear-fuel-cell-homogenization-calculation
3d-simulation-molten-metal-feezing-behaviour-using-finite-volume-particle-method
heat-transfer-benchmark-problems-verification-finite-volume-particle-fvp-method-based-code
particle-based-simulations-molten-metal-flows-solidification
3d-simulations-solid-melt-mixture-flow-melt-solidification-using-finite-volume-particle-method
Preliminary Study of Lead-oxide Cooled Fast Reactor with Natural Uranium As An Input Fuel with Reactor Shuffling Strategy
Heat Transfer Problems Verification of Finite Volume Particle (FVP) Method-based Code
Bidang Pengabdian

No.

Judul

Sumber Dana

Keterangan

1.

Workshop Pengajaran Active Learning untuk Guru dan Calon Guru Sains, Fisika dan Biologi SMA dan SMP di Yogyakarta dan sekitarnya

AMINEF

Dilaksanakan di FMIPA UNY, bulan April 2015

2.

Pelatihan Perangkat Praktikum Fisika tingkat SMP untuk Mata Pelajaran Listrik Magnet, Optik dan Mekanika

MIPA UNY

Dilaksanakan di SMPN 3 Kalasan, bulan Oktober 2016

 

File Bidang Pengabdian :
workshop-pengajaran-active-learning-untuk-guru-dan-calon-guru-sains-fisika-dan-biologi-sma-dan-smp-d
Karya Terindex Google Scholar
Judul Sitasi
A design study of Pb-Bi-cooled fast reactors with natural uranium as the fuel cycle input15
The utilization of thorium for long-life small thermal reactors without on-site refueling12
Feasibility Analysis of Nuclear Energy System for Developing Countries Which Can Utilize Natural Uranium/Thorium Efficiently Without Embedded Enrichment plant nor Reprocessing plants.7
3D simulation of solid-melt mixture flow with melt solidification using a finite volume particle method4
Fission Yield Calculation Method and its Effect in Nuclear Fuel Cell Homogenization Calculation2
Particle-based Simulations of Molten Metal Flows with Solidification1
The Fission Products (FP) group constant treatment for long-life Pb-Bi-cooled fast power reactors1
Preliminary Study of Lead-Oxide Cooled Fast Reactor with Natural Uranium as an Input Fuel with Reactor Shuffling Strategy0
Feasibility Design Study of Long Life BWR with Natural Uranium/Thorium as Fuel Cycle Input0
Heat Transfer Problems Verification of Finite Volume Particle (FVP) Method-based Code0
ICONE19-43981 Numerical Simulation of Effective Viscosity in Solid-Fluid Mixture Flows Using Finite Volume Particle Method0
3D Simulation of Molten Metal Freezing Behaviour Using Finite Volume Particle Method0
Flexible modified candle burnup scheme based long life Pb-Bi cooled fast reactor with natural uranium as fuel cycle input employing coupled core0
A design study of Pb-Bi-cooled fast reactors with natural uranium as the fuel cycle input0
Studi Desain Reaktor Cepat Berpendingin Pb-Bi Berbasis Bahan Bakar Uranium Alam Menggunakan Strategi Shuffling0
Numerical simulation of effective viscosity in solid-fluid mixture flows using finite volume particle method0
Heat Transfer Benchmark Problems Verification of Finite Volume Particle (FVP) Method-based Code0