Follow
Donny Hartanto
Donny Hartanto
Nuclear Energy and Fuel Cycle Division, Oak Ridge National Laboratory
Verified email at ornl.gov - Homepage
Title
Cited by
Cited by
Year
A Conceptual Study of a Supercritical CO2-Cooled Micro Modular Reactor
H Yu, D Hartanto, K Jangsik
Energies 8 (12), 13938-13952, 2015
392015
Kinetics parameters evaluation on the first core of the RSG GAS (MPR-30) using continuous energy Monte Carlo method
PH Liem, T Surbakti, D Hartanto
Progress in Nuclear Energy 109, 196-203, 2018
362018
Comparison of different glass materials to protect the operators from gamma-rays in the PET using MCNP code
M Zubair, E Ahmed, D Hartanto
Radiation Physics and Chemistry 190, 109818, 2022
312022
Alternative reflectors for a compact sodium-cooled breed-and-burn fast reactor
D Hartanto, Y Kim
Annals of Nuclear Energy 76, 113-124, 2015
302015
Neutronics optimization and characterization of a long‐life SCO2‐cooled micro modular reactor
Y Kim, D Hartanto, H Yu
International Journal of Energy Research 41 (7), 976-984, 2017
242017
Neutronics and transient analyses of a supercritical CO2-cooled micro modular reactor (MMR)
H Yu, D Hartanto, BS Oh, JI Lee, Y Kim
Energy Procedia 131, 21-28, 2017
212017
Sensitivity and uncertainty analysis on the first core criticality of the RSG GAS multipurpose research reactor
PH Liem, Zuhair, D Hartanto
Progress in Nuclear Energy 114, 46-60, 2019
192019
On the performance of nanofluids in APR 1400 PLUS7 assembly: Neutronics
BA Khuwaileh, FI Al-Hamadi, D Hartanto, Z Said, M Ali
Annals of Nuclear Energy 144, 107508, 2020
182020
On the particle swarm optimization of cask shielding design for a prototype sodium-cooled fast reactor
DW Lim, CW Lee, JY Lim, D Hartanto
Nuclear Engineering and Technology 51 (1), 284-292, 2019
182019
A compact breed and burn fast reactor using spent nuclear fuel blanket
D Hartanto, Y Kim
PHYSOR 2012, 2012
182012
A comparative physics study for an innovative sodium‐cooled fast reactor (iSFR)
D Hartanto, C Kim, Y Kim
International Journal of Energy Research 42 (1), 151-162, 2018
172018
A high-fidelity Monte Carlo evaluation of CANDU-6 safety parameters
Y Kim, D Hartanto
PHYSOR 2012, 2012
172012
Neutronics evaluation of a super-deep-burn with TRU fully ceramic microencapsulated (FCM) fuel in CANDU
D Hartanto, Y Kim, F Venneri
Progress in Nuclear Energy 83, 261-269, 2015
152015
Uranium enrichment reduction in the prototype gen-IV sodium-cooled fast reactor (PGSFR) with PBO reflector
C Kim, D Hartanto, Y Kim
Nuclear Engineering and Technology 48 (2), 351-359, 2016
132016
Re-evaluation of the Fuel Temperature Coefficient of CANDU 6
YH Kim, D Hartanto
Transactions of the Korean Nuclear Society Autumn Meeting 2011, 2011
132011
Analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS using the Serpent Monte Carlo code and the ENDF/B-VIII. 0 nuclear data library
D Hartanto, PH Liem
Nuclear Engineering and Technology 52 (12), 2725-2732, 2020
122020
Development of a PARCS/Serpent model for neutronics analysis of the Dalat nuclear research reactor
VP Tran, KC Nguyen, D Hartanto, HN Tran, VT Tran, VK Hoang, ...
Nuclear Science and Technique 32, 15, 2021
112021
An optimization study on the excess reactivity in a linear breed-and-burn fast reactor (B&BR)
D Hartanto, C Kim, Y Kim
Annals of Nuclear Energy 94, 62-71, 2016
112016
Impacts of burnup-dependent swelling of metallic fuel on the performance of a compact breed-and-burn fast reactor
D Hartanto, W Heo, C Kim, Y Kim
Nuclear Engineering and Technology 48 (2), 330-338, 2016
112016
Analysis of the excess reactivity and control rod worth of RSG-GAS equilibrium silicide core using Continuous-Energy Monte Carlo Serpent2 code
TM Sembiring, S Pinem, D Hartanto, PH Liem
Annals of Nuclear Energy 154, 108107, 2021
102021
The system can't perform the operation now. Try again later.
Articles 1–20