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DIAN FITRIYANI

Universitas Andalas S2 - Fisika SINTA ID : 5998362
554
SINTA Score Overall
139
SINTA Score 3Yr
515
Affil Score
130
Affil Score 3Yr
Latest number of publications
  Scopus Analysis  

Neutron flux distribution of slab reactor core using one-dimensional multi-group diffusion equation in the thermal energy region
Q4 Journal AIP Conference Proceedings
Author Order : 3 of 5     Creator : Shafii M.A.
2022 1 cited
Study of Neutronic Performance of Sodium-Cooled Fast Reactor Design for Various Output Power Using Radial Fuel Shuffling Strategy
Q4 Journal Journal of Physics: Conference Series
Author Order : 4 of 5     Creator : Ali Shafii M.
2021 1 cited
Calculation of collision probability matrix of nuclear fuel cell as a function of neutron energy group using flat flux model
Q3 Journal International Journal of Mechanics
Author Order : 2 of 4     Creator : Shafii M.A.
2021 0 cited
De-aliasing method for Doppler velocity data of echocardiography in echodynamography
Q4 Journal AIP Conference Proceedings
Author Order : 2 of 5     Creator : Oktamuliani S.
2021 0 cited
Characteristics of neutron diffusion coefficient as a function of energy group in the one-dimensional multi-group diffusion equation of finite slab reactor core
Q4 Journal Journal of Physics: Conference Series
Author Order : 3 of 5     Creator : Shafii M.A.
2021 2 cited
Thermalhydraulic performance of small fast reactor base on various types of liquid metal coolant materials
Q4 Journal AIP Conference Proceedings
Author Order : 1 of 5     Creator : Fitriyani D.
2019 0 cited
Neutron flux distribution calculation for various spatial mesh of finite slab geometry using one-dimensional diffusion equation
Q4 Journal AIP Conference Proceedings
Author Order : 3 of 4     Creator : Shafii M.
2019 3 cited
Neutron distribution in the nuclear fuel cell using collision probability method with quadratic flux approach
Q4 Journal IOP Conference Series: Materials Science and Engineering
Author Order : 2 of 4     Creator : Shafii M.
2017 2 cited
Theoretical analysis of integral neutron transport equation using collision probability method with quadratic flux approach
Q4 Journal AIP Conference Proceedings
Author Order : 4 of 6     Creator : Shafii M.
2014 3 cited
Optimization of 200 MWth and 250 MWt ship based small long life NPP
Q4 Journal AIP Conference Proceedings
Author Order : 1 of 2     Creator : Fitriyani D.
2010 0 cited
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Summary

Article Quartile
Research Output
  Scopus GScholar WOS
Article 13 57 0
Citation 28 160 0
Cited Document 7 34 0
H-Index 3 7
i10-Index 1 5
G-Index 1 1
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