Zobrazeno 1 - 10
of 29
pro vyhledávání: '"R. Andika Putra Dwijayanto"'
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:
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
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:
Kerntechnik. 87:305-315
Transmutation technology has been developed to address the issue of long-term safety of nuclear waste disposal in geological repository. Transuranic (TRU) transmutation in thermal neutron spectrum can be considered more beneficial at the present time
Publikováno v:
Tri Dasa Mega, Vol 22, Iss 2, Pp 54-60 (2020)
Molten salt reactor (MSR) is often associated with thorium fuel cycle, thanks to its excellent neutron economy and online reprocessing capability. However, since 233U, the fissile used in pure thorium fuel cycle, is not commercially available, the MS
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