Dwi Irwanto
TitleCited byYear
Comparison of Monte Carlo calculation methods for effective delayed neutron fraction
Y Nagaya, G Chiba, T Mori, D Irwanto, K Nakajima
Annals of Nuclear Energy 37 (10), 1308-1315, 2010
312010
Burnup characteristics of a Peu à Peu fuel loading scheme in a 110MWt simplified pebble bed reactor
D Irwanto, T Obara
Journal of nuclear science and technology 48 (11), 1385-1395, 2011
142011
Preliminary Neutronic Design of High Burnup OTTO Cycle Pebble Bed Reactor
T Setiadipura, D Irwanto, Z Zuhair
Atom Indonesia 41 (1), 7-15, 2015
132015
Decay heat removal without forced cooling on a small simplified PBR with an accumulative fuel loading scheme
D Irwanto, T Obara
Annals of Nuclear Energy 60, 383-395, 2013
92013
Burnup characteristics and fuel cycle economics of mixed uranium–thorium fuel in a simplified small pebble bed reactor
D Irwanto, T Obara
Journal of Nuclear Science and Technology 49 (2), 222-229, 2012
92012
Study on calculation methods for effective delayed neutron fraction
D Irwanto, T Obara, G Chiba, Y Nagaya
Proc. 2009 Annual Meeting of the Atomic Energy Society of Japan, Tokyo …, 2009
82009
Burnup Characteristics of Peu-à-Peu Fuel Loading Scheme in Small PBR
D Irwanto, T Obara, Y Kato, I Yamanaka
Transactions of the American Nuclear Society 103, 791-792, 2010
52010
Major outcomes from OECD/NEA ROSA and ROSA-2 Projects
H Nakamura, T Takeda, A Satou, M Ishigaki, S Abe, D Irwanto
Proceedings of the 15th International Topical Meeting on Nuclear Reactor …, 2013
42013
Design Study of 200MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel Long Life without Refueling
RD Syarifah, Y Yulianto, Z Su’ud, K Basar, D Irwanto
MATEC Web of Conferences 82, 03008, 2016
32016
Comparison of several thermal conductivity constants for thermal hydraulic calculation of pebble bed reactor
D Irwanto, T Setiadipura, A Pramutadi
Journal of Physics: Conference Series 877 (1), 012031, 2017
22017
Neutronic analysis of thorium nitride (Th, U233) N fuel for 500MWth gas cooled fast reactor (GFR) long life without refueling
RD Syarifah, Y Yulianto, Z Su’ud, K Basar, D Irwanto
Key Engineering Materials 733, 47-50, 2017
22017
Fuel Fraction Analysis of 500 MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel without Refueling
RD Syarifah, Z Su’ud, K Basar, D Irwanto
Journal of Physics: Conference Series 799 (1), 012022, 2017
22017
The prospect of uranium nitride (UN-PuN) fuel for 25-100MWe gas cooled fast reactor long life without refuelling
RD Syarifah, Z Su'ud, K Basar, D Irwanto
Journal of Physics: Conference Series 776 (1), 012103, 2016
22016
Comparison of uranium plutonium nitride (U‐Pu‐N) and thorium nitride (Th‐N) fuel for 500 MWth gas‐cooled fast reactor (GFR) long life without refueling
RD Syarifah, Z Su'ud, K Basar, D Irwanto, SC Pattipawaej, M Ilham
International Journal of Energy Research 42 (1), 214-220, 2018
12018
Comparative Studies on UO2 Fueled HTTR Several Nuclear Data Libraries
AN Hidayati, PA Prastyo, A Waris, D Irwanto
Journal of Physics: Conference Series 877 (1), 012049, 2017
12017
Delayed Neutrons Effect on Power Reactor with Variation of Fluid Fuel Velocity at MSR Fuji-12
IK Aji, S Pramuditya, D Irwanto, A Waris
Journal of Physics: Conference Series 799 (1), 012004, 2017
12017
Melting Penetration Simulation of Fe-U System at High Temperature Using MPS_LER
APA Mustari, A Yamaji, D Irwanto
Journal of Physics: Conference Series 739 (1), 012016, 2016
12016
Burnup Characteristics of Thorium Fuel in a Small PBR with Peu-a-Peu Fuel-Loading Scheme
D Irwanto, T Obara
Transactions of the American Nuclear Society 105, 1105-1106, 2011
12011
Benchmarking of effective delayed neutron fraction with deterministic method
D Irwanto, T Obara, G Chiba
12009
Design Study of Long Life Thorium-based Pressurized Water Reactor (PWR) Using Annular Fuel System and Protactanium as Burnable Poison
D Irwanto, Z Su’ud
Proceedings of Asian Physics Symposium, Bandung, 366-370, 2005
12005
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Articles 1–20