Follow
Anhar Riza Antariksawan
Anhar Riza Antariksawan
Researcher @BATAN
Verified email at brin.go.id
Title
Cited by
Cited by
Year
Passive cooling system in a nuclear spent fuel pool using a vertical straight wickless-heat pipe
MH Kusuma, N Putra, AR Antariksawan, RA Koestoer, S Widodo, ...
International Journal of Thermal Sciences 126, 162-171, 2018
672018
Investigation of the thermal performance of a vertical two-phase closed thermosyphon as a passive cooling system for a nuclear reactor spent fuel storage pool
MH Kusuma, N Putra, AR Antariksawan, FA Imawan
Nuclear Engineering and Technology 49 (3), 476-483, 2017
612017
Estimation of natural circulation flow based on temperature in the FASSIP-02 large-scale test loop facility
M Juarsa, AR Antariksawan, MH Kusuma, D Haryanto, N Putra
IOP Conference Series: Earth and Environmental Science 105 (1), 012091, 2018
362018
Validation of RELAP/SCAPSIM/MOD3. 4 for research reactor applications
AR Antariksawan, MQ Huda, T Liu, J Zmitkova, CM Allison, JK Hohorst
Proceedings of the 13th International Conference on Nuclear Engineering …, 2005
322005
Simulation of Operational Conditions of FASSIP-02 Natural Circulation Cooling System Experimental Loop
AR Antariksawan, S Widodo, M Juarsa, D Haryanto, MH Kusuma, N Putra
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear …, 2018
212018
Numerical study on natural circulation characteristics in FASSIP-02 experimental facility using RELAP5 code
AR Antariksawan, S Widodo, M Juarsa, D Haryanto, MH Kusuma, N Putra
IOP Conference Series: Earth and Environmental Science 105 (1), 012090, 2018
182018
Susyadi, FA Imawan, Investigation of the thermal performance of a vertical two-phase closed thermosyphon as a passive cooling system for a nuclear reactor spent fuel storage pool
MH Kusuma, N Putra, AR Antariksawan
Nucl. Eng. Technol 49, 476-483, 2017
152017
Nuclear security culture and Batan’s assessment: Batan’s experience
AR Antariksawan
International Journal of Nuclear Security 2 (2), 4, 2016
142016
Design of passive residual heat removal systems and application of two-phase thermosyphons: A review
W Surip, N Putra, AR Antariksawan
Progress in Nuclear Energy 154, 104473, 2022
132022
Simulation of heat flux effect in straight heat pipe as passive residual heat removal system in light water reactor using RELAP5 Mod 3.2
MH Kusuma, N Putra, S Widodo, AR Antariksawan
Applied Mechanics and Materials 819, 122-126, 2016
132016
TRIGA 2000 Research Reactor Thermal-hydraulic Analysis Using RELAP/SCDAPSIM/MOD3. 4
AR Antariksawan, E Umar, S Widodo, M Juarsa, MH Kusuma
International Journal of Technology 8 (4), 698-708, 2017
112017
Experimental study on the effect of gap size to CCFL and CHF in a vertical of narrow rectangular channel during quenching process
M Juarsa, N Putra, WN Septiadi, AR Antariksawan
Annals of Nuclear Energy 72, 391-400, 2014
112014
Study on Boiling Heat Transfer During Reflooding Process in QUEEN Test Section
M Juarsa, AR Antariksawan, J P., I W., E S., Kiswanta
International Congress on Advances in Nuclear Power Plant (ICAPP 2005), 2005
102005
Preliminary investigation on natural circulation flow using CFD and calculation base on experimental data pre-FASSIP-02
M Juarsa, AR Antariksawan, MH Kusuma, N Putra, PP Moniaga
Journal of Physics: Conference Series 1198 (2), 022073, 2019
92019
Evaluasi Disain Sistem Pendingin Reaktor Triga Mark II Bandung Daya 2 MW
AR Antariksawan, P Aliq, I Handoyo
Prosiding Presentasi Ilmiah Teknologi Keselamatan Nuklir-V 28, 1410-0533, 2000
92000
Depressurization Analyses of PWR Station Blackout with MELCOR 1.8. 4
AR ANTARIKSAWAN, A HIDAKA, K MORIYAMA, K HASHIMOTO
JAERI-Tech 11, 2001
82001
Preliminary investigation of natural circulation stability in FASSIP-01 experimental facility using RELAP5 code
AR Antariksawan, S Widodo, M Juarsa, G Giarno, MH Kusuma, N Putra
AIP Conference Proceedings 2001 (1), 2018
72018
Kata Pengantar
BM Rahman
Komaruddin Hidayat and Wahyuni Nafis. Agama Masa Depan: Perspektif Filsafat …, 2006
72006
Analisis Kecelakaan Kehilangan Catu Daya Dengan Kebocoran Seal Pompa Pada PWR Menggunakan MELCOR1.8.4
AR Antariksawan
Seminar ke-VI Teknologi dan Keselamatan PLTN Serta Fasilitas Penunjang, 2000
7*2000
Experimental investigation on the thermohydraulic parameters of Kartini research reactor under variation of the primary pump flow
B Riyono, R Pulungan, A Dharmawan, AR Antariksawan
Applied Thermal Engineering 213, 118674, 2022
62022
The system can't perform the operation now. Try again later.
Articles 1–20