Fisika

UNIVERSITAS JEMBER KAB. JEMBER - JAWA TIMUR, ID CODE PRODI : 45102 CODE PT : 001025
8
Authors
13.739
SINTA Score Overall
2.698
SINTA Score 3Yr
1.717
SINTA Score Overall Productivity
337
SINTA Score 3Yr Productivity
Latest number of publications
Semiconducting biomass-based amorphous carbon films and their potential application in photovoltaic devices
Q1 Journal Materials Science in Semiconductor Processing
Creator : Purwandari E.
2025 0 cited
A Physical Reason Why Molten Lead-bismuth Alloy has Advantage of Being Used as a Potential Coolant for Fast Nuclear Reactors Design
Q4 Journal Pakistan Journal of Scientific and Industrial Research Series A: Physical Sciences
Creator : Arkundato A.
2024 0 cited
OPTIMIZING DYE-SENSITIZED SOLAR CELL EFFICIENCY THROUGH TiO2/CuS DOPING: EFFECTS OF INTERNAL PARAMETER VARIATIONS
Q3 Journal Eastern-European Journal of Enterprise Technologies
Creator : Supriyanto E.
2024 0 cited
The Effect of Adding Minor Actinide Fuel Rods on GFR Reactor in Radiopharmaceutical Waste Production Using OpenMC Program
Q2 Journal Science and Technology Indonesia
Creator : Syarifah R.D.
2024 0 cited
Encapsulation of neem seed oil in alginate/lignin-black liquor matrix
Q4 Journal AIP Conference Proceedings
Creator : Ghosiyah A.
2024 0 cited
Milling effect of hydroxyapatite bioceramic extracted from fish bone waste
Q4 Journal AIP Conference Proceedings
Creator : Yulianingtias R.
2024 0 cited
ANALYSIS OF VARIATION MINOR ACTINIDE PIN CONFIGURATIONS Np-237, AM-241, AND Cm-244 IN UN-PuN FUELED PRESSURIZED WATER REACTOR
Q3 Journal EUREKA, Physics and Engineering
Creator : Syarifah R.D.
2024 0 cited
Fe-Cr-Al-Ti STEEL FOR APPLICATIONS IN LEAD-COOLED FAST NUCLEAR-REACTOR DESIGN: A MOLECULAR DYNAMICS STUDY
Q3 Journal International Journal on Technical and Physical Problems of Engineering
Creator : Arkundato A.
2024 0 cited
Neutronic Analysis for the Radial Direction Heterogeneous Core Configuration of GFR with Thorium Fuel
Q3 Journal Journal of Physics: Conference Series
Creator : Angelina T.E.
2024 0 cited
Calculation of neutron flux distribution and diffusion coefficient in the slab reactor core using multi-group diffusion equation with Jacobi method
Q4 Journal AIP Conference Proceedings
Creator : Shafii M.A.
2024 0 cited
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Research Output
  Scopus GScholar WOS
Article 154 1,874 71
Citation 1,403 10,051 970
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