Zobrazeno 1 - 10
of 77
pro vyhledávání: '"Donny Hartanto"'
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 5, Pp 1775-1782 (2023)
Several reactor physics commissioning experiments were conducted to obtain the neutronic parameters at the beginning of the G.A. Siwabessy Multi-purpose Reactor (RSG-GAS) operation. These parameters are essential for the reactor to safety operate. Le
Externí odkaz:
https://doaj.org/article/a2797f97663f48a4aec1ed4291f0d376
Autor:
Theodore M. Besmann, Juliano Schorne-Pinto, Mina Aziziha, Amir M. Mofrad, Ronald E. Booth, Jacob A. Yingling, Jorge Paz Soldan Palma, Clara M. Dixon, Jack A. Wilson, Donny Hartanto
Publikováno v:
Materials, Vol 17, Iss 2, p 495 (2024)
The extensively evaluated and consistent thermodynamic database, the Molten Salt Thermal Properties Database—Thermochemical (MSTDB-TC), was used along with additional thermodynamic values from other sources as examples of ways to examine molten sal
Externí odkaz:
https://doaj.org/article/74fea2cf0ed141daa8e5297f1f0a3d7b
Publikováno v:
South African Journal of Chemical Engineering, Vol 41, Iss , Pp 235-243 (2022)
In August 2020, the first Barakah Nuclear Power Plant (BNPP) unit was connected to the grid and started supplying electricity. The BNPP site consists of 4 pressurized water reactor units, and each unit generates electricity up to 1400 MWe power. Conc
Externí odkaz:
https://doaj.org/article/f42e5da51d354a40938d2693fd7001a0
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 2, Pp 764-769 (2022)
The United Arab Emirates is currently building and operating four units of the APR-1400 developed by a South Korean vendor, Korea Electric Power Corporation (KEPCO). This paper attempts to perform APR-1400 reactor core analysis by using the well-know
Externí odkaz:
https://doaj.org/article/9900501710bd4de8beae6edd2f2f7db1
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 7, Pp 2095-2103 (2021)
A small power ADS design using thorium oxide and diluent matrix reprocessed fuel is proposed for a high transmutation rate, small reactivity swing, and strong safety features. Two fuel matrices (CERCER and CERMET) and different recycled fuel composit
Externí odkaz:
https://doaj.org/article/840393b3d87b479abc4e1ef6bb299ce5
Autor:
Donny Hartanto, Peng Hong Liem
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 12, Pp 2725-2732 (2020)
This paper presents the neutronics benchmark analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS (Reaktor Serba Guna G.A. Siwabessy) calculated by the Serpent Monte Carlo code and the newly released ENDF/B-VIII.0 nuclea
Externí odkaz:
https://doaj.org/article/a0bd8d9f802b4b12a6abb4c527d86a21
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2022 (2022)
Steady-state and transient analysis of reactor core under Reactivity-Initiated Accident (RIA) conditions are important for reactor operation safety. The reactor dynamics are influenced by neutronic and thermal-hydraulic aspects of the core. In this s
Externí odkaz:
https://doaj.org/article/700d9405fef5453681e717f90bd5b356
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 4, Pp 968-976 (2019)
This paper presents a number of verification case studies for a recently developed sensitivity/uncertainty code package. The code package, ROMUSE (Reduced Order Modeling based Uncertainty/Sensitivity Estimator) is an effort to provide an analysis too
Externí odkaz:
https://doaj.org/article/496783dec8d64c84978dc8dc129f51b0
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 1, Pp 284-292 (2019)
For the continuous operation of a nuclear reactor, burnt fuel needs to be replaced with fresh fuel, where appropriate (ex-vessel) fuel handling is required. Particularly for the Sodium-cooled Fast Reactor (SFR) refueling, its process has unique chall
Externí odkaz:
https://doaj.org/article/7ab20823a40845a98958648802198209
Autor:
Thanh Mai Vu, Donny Hartanto
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2021 (2021)
Previously, the neutronics design of a small and compact linear breed-and-burn fast reactor (B&BR) was completed. The reactor produces 400 MWth power, and it can operate with excess reactivity of less than 1$ for more than 50 years without refuelling
Externí odkaz:
https://doaj.org/article/e165e48e0ff743f8a43bcedea55ada77