Zobrazeno 1 - 10
of 10
pro vyhledávání: '"R. A. P. Dwijayanto"'
Publikováno v:
Atom Indonesia, Vol 47, Iss 3, Pp 191-197 (2021)
Passive Compact Molten Salt Reactor (PCMSR) is a thermal breeder molten salt reactor (MSR) developed in Universitas Gadjah Mada, Indonesia, run in thorium fuel cycle. Its design was initially developed using deterministic code SRAC2006 but has never
Externí odkaz:
https://doaj.org/article/96582479b015446a922f931e21e292b8
Autor:
Andang Widi Harto, Alexander Agung, Sihana, M Yayan Adi Putra, Rayhan Alghiffari Azizi, Diva Jati Kanaya, Alfonsus Rahmadi Putranto Gusti, R Andika Putra Dwijayanto
Publikováno v:
Heliyon, Vol 10, Iss 9, Pp e30707- (2024)
The GAMA Microreactor is a low-power nuclear power plant dedicated for remote area with a power output of 300 kWe. The primary characteristics of the GAMA Microreactor are its system compactness, design simplicity, and safe operation without moving p
Externí odkaz:
https://doaj.org/article/5e42de81059547a1bb091cf9ba529cfd
Autor:
R. Andika Putra Dwijayanto
Publikováno v:
Sustainability Science and Resources, Vol 4, Iss 4, Pp 47-59 (2023)
In the wake of climate change and global warming, various alternatives are being considered as a potential replacement for fossil fuels. Despite often being overlooked, nuclear power offers many benefits as a low-carbon energy source. Being a thermal
Externí odkaz:
https://doaj.org/article/1fbda844597e43c79330988c6f492840
Publikováno v:
Computational and Experimental Research in Materials and Renewable Energy, Vol 4, Iss 1, Pp 8-20 (2021)
One of the rarely explored molten salt reactor (MSR) designs is the molten chloride fast reactor (MCFR). This MSR design employs chloride salt instead of fluoride and operated in a fast spectrum. MCFR brings all the advantages of an MSR including bre
Externí odkaz:
https://doaj.org/article/068d81b9e7a242bbafde1d839ed91d8d
Publikováno v:
Urania, Vol 25, Iss 2 (2019)
CHARACTERISTICS OF RADIONUCLIDES ON THORIUM-CYCLE EXPERIMENTAL POWER REACTOR SPENT FUEL. There are several options of nuclear fuel utilisation in the HTGR-based Experimental Power Reactor (Reaktor Daya Eksperimental/RDE). Although mainly RDE utilises
Externí odkaz:
https://doaj.org/article/9196dd24f7bf41e9a4e994afd7da38fd
Publikováno v:
Atom Indonesia, Vol 47, Iss 3, Pp 191-197 (2021)
Passive Compact Molten Salt Reactor (PCMSR) is a thermal breeder molten salt reactor (MSR) developed in Universitas Gadjah Mada, Indonesia, run in thorium fuel cycle. Its design was initially developed using deterministic code SRAC2006 but has never
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8abf7209dd2a5a76fb75564cf9960c3c
https://doi.org/10.17146/aij.2021.1122
https://doi.org/10.17146/aij.2021.1122
Publikováno v:
Journal of Physics: Conference Series. 2072:012001
The existence of Tl-208 in thorium fuel cycle is a double-edged sword. Tl-208 is a high-energy 2.6 MeV gamma emitter, which acts as an effective proliferation barrier while simultaneously complicating the handling of the spent fuel. To ensure the saf
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::92f8a971687685058a621d48e8b5edd2
https://doi.org/10.1088/1742-6596/2072/1/012001
https://doi.org/10.1088/1742-6596/2072/1/012001
Publikováno v:
AIP Conference Proceedings.
Based on its superior characteristics and to provide core outlet temperature no less than 1000 °C for thermochemical hydrogen production, ZrC becomes a promising candidate to replace SiC coating layer of TRISO coated fuel particles. This paper aimed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::450d314b39ae1b588f2fb7c2d4e8b7f7
https://doi.org/10.1063/1.5135514
https://doi.org/10.1063/1.5135514
Publikováno v:
Urania, Vol 28, Iss 1, Pp 45-56 (2022)
EFFECTS OF FUEL DENSITY ON REACTIVITY COEFFICIENTS AND KINETIC PARAMETERS OF PEBBLE BED REACTOR. Few decades ago a large number of nuclear reactors were designed to use HEU as the fuel. But the use of HEU is being discouraged since it can be used as
Externí odkaz:
https://doaj.org/article/c9765347c6a94c1abf91484594c4a972
Publikováno v:
Urania, Vol 27, Iss 3, Pp 165-176 (2021)
STUDY ON CRITICALITY AND NEUTRONIC SAFETY PARAMETERS OF NUSCALE FUEL ASSEMBLY. NuScale, a typical Pressurized Water Reactor (PWR) Small Modular Reactors (SMRs), offers a new opportunity for the future of nuclear industry. With 160 MW thermal power, N
Externí odkaz:
https://doaj.org/article/75ea881bae6549ef90a41842b10b61d3