Rekayasa Nuklir

INSTITUT TEKNOLOGI BANDUNG KOTA BANDUNG - JAWA BARAT, ID CODE PRODI : 37001 CODE PT : 002001
6
Authors
33.946
SINTA Score Overall
3.987
SINTA Score 3Yr
5.658
SINTA Score Overall Productivity
665
SINTA Score 3Yr Productivity
Latest number of publication
Enhancing the neutronic performance of SMART Small modular reactor using alternative fuel material
WOS.SCI Edition   Core Collection ANNALS OF NUCLEAR ENERGY
Authors : Widiawati, N; Trianti, N; Luthfi, W; Zuhair; Wafda, H; Nagara, N; Roswita, F; Miftasani, F...
FEB 2025 0 cited Scopus Indexed DOI : 10.1016/j.anucene.2024.110895
Exploring the Impact of Motion Parameter Variations in Virtual Reality Content on Visually Induced Motion Sickness: An Electroencephalography Signal Analysis Approach
WOS.ESCI Edition   Core Collection INTERNATIONAL JOURNAL OF ONLINE AND BIOMEDICAL ENGINEERING
Authors : Suwandi, GRF; Khotimah, SN; Haryanto, F; Suprijadi;
2024 0 cited DOI : 10.3991/ijoe.v20i12.49773
A passive single-cylindrical neutron spectrometer for photoneutron spectrometry in 10 MV Elekta Precise Linac head
WOS.SCI Edition   Core Collection NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT
Authors : Tursinah, R; Permana, S; Suud, Z; Maulana, A; Sukmabuana, P; Lesmana, H; Afham, A; Laksono, T;
AUG 2024 2 cited Scopus Indexed DOI : 10.1016/j.nima.2024.169519
Study the Effects of Age, Gender, and Body Mass Index on Heart Rate
WOS.ESCI Edition   Core Collection MALAYSIAN JOURNAL OF FUNDAMENTAL AND APPLIED SCIENCES
Authors : Nahdiyya, F; Khotimah, SN;
MAY-JUN 2024 0 cited Scopus Indexed DOI : 10.11113/mjfas.v20n3.3381
3-Dimensional full core neutronic analysis for uranium nitride fuel CANDLE reactor using Monte Carlo MCNP6 code
WOS.SCI Edition   Core Collection NUCLEAR ENGINEERING AND DESIGN
Authors : Afifah, M; Su'ud, Z; Trianti, N; Irwanto, D;
AUG 15 2024 1 cited Scopus Indexed DOI : 10.1016/j.nucengdes.2024.113340
Comparison of the neutronic properties of the (Th-233U)O2, (Th-233U)C, and (Th-233U)N fuels in small long-life PWR cores with 300, 400, and 500 MWth of power
WOS.SCI Edition   Core Collection NUKLEONIKA
Authors : Lapanporo, BP; Su'ud, Z; Mustari, APA;
MAR 1 2024 0 cited Scopus Indexed DOI : 10.2478/nuka-2024-0001
Neutronic and thermal-hydraulic analysis for TRIGA Mark II in subcooled nucleate boiling condition
WOS.SCI Edition   Core Collection NUCLEAR ENGINEERING AND DESIGN
Authors : Trianti, N; Basuki, P; Maulana, A; Pane, JS; Umar, E; Su'ud, Z;
MAY 2024 1 cited Scopus Indexed DOI : 10.1016/j.nucengdes.2024.113092
Design and validation of a single cylindrical neutron spectrometer using a gold activation foil
WOS.SCI Edition   Core Collection RADIATION MEASUREMENTS
Authors : Tursinah, R; Permana, S; Su'ud, Z; Maulana, A; Sukmabuana, P;
FEB 2024 3 cited Scopus Indexed DOI : 10.1016/j.radmeas.2024.107053
Design study of small modular gas-cooled fast reactor employing modified CANDLE burnup with radial direction shuffling scheme
WOS.SCI Edition   Core Collection KERNTECHNIK
Authors : Irka, FH; Su'ud, Z; Irwanto, D; Khotimah, SN; Sekimoto, H;
OCT 26 2023 0 cited Scopus Indexed DOI : 10.1515/kern-2023-0017
Comparison of thermal-hydraulic calculation in 100 MWt thorium-based HTGR using SiC and ZrC TRISO coated fuel particle
WOS.SCI Edition   Core Collection NUCLEAR ENGINEERING AND DESIGN
Authors : Miftasani, F; Widiawati, N; Trianti, N; Salsabila, DS; Setiadipura, T; Wulandari, C; Irwan...
OCT 2023 3 cited Scopus Indexed DOI : 10.1016/j.nucengdes.2023.112463
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Article 481 1,361 300
Citation 3,013 5,888 1,387
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