Zobrazeno 1 - 10
of 19
pro vyhledávání: '"Andi Sofrany Ekariansyah"'
PRELIMINARY ASSESSMENT OF ENGINEERED SAFETY FEATURES AGAINST STATION BLACKOUT IN SELECTED PWR MODELS
Publikováno v:
Tri Dasa Mega, Vol 23, Iss 2, Pp 47-56 (2021)
The 2011 Fukushima accident did not prevent countries to construct new nuclear power plants (NPPs) as part of the electricity generation system. Based on the IAEA database, there are a total of 44 units of PWR type NPPs whose constructions are starte
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e9a1a2d2e59edb031e63c2dd25e008fc
http://jurnal.batan.go.id/index.php/tridam/article/view/6204
http://jurnal.batan.go.id/index.php/tridam/article/view/6204
Autor:
Anwar Budianto, Andi Sofrany Ekariansyah, Susyadi Susyadi, Hendro Tjahjono, Surip Widodo, Puradwi Ismu Wahyono
Publikováno v:
Tri Dasa Mega, Vol 20, Iss 3, Pp 159-165 (2018)
High Temperature Gas Cooled Reactor (HTGR) is a high temperature reactor type having nuclear fuels formed by small particles containing uranium in the core. One of HTGR designs is Pebble Bed Reactor (PBR), which utilizes helium gas flowing between pe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::126f759ade750624e4516eced2a7ce0a
http://jurnal.batan.go.id/index.php/tridam/article/view/4665
http://jurnal.batan.go.id/index.php/tridam/article/view/4665
Publikováno v:
AIP Conference Proceedings.
Analysis on inadvertent operation of decay heat removal system in NuScale reactor has been carried out through numerical simulations using the RELAP5 code. The model used includes primary system, secondary system, decay heat removal system (DHRS) and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d09ab4f7cf2a740f401b4999d32e2ca1
https://doi.org/10.1063/1.5135523
https://doi.org/10.1063/1.5135523
Publikováno v:
AIP Conference Proceedings.
The Indonesia Nuclear Energy Agency (BATAN) has been being managed to design the so called Experimental Power Reactor (EPR), which is a High Temperature Gas Cooled Reactor (HTGR) type with the thermal power of 10 MW. The purpose of the reactor develo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2c971e797766fad7b333517c3c2fac79
https://doi.org/10.1063/1.5135517
https://doi.org/10.1063/1.5135517
Autor:
Andi Sofrany Ekariansyah, Rahayu Kusumastuti, DH Dedy Haryanto, Mukhsinun Hadi Kusuma, Susyadi, Surip Widodo, Hendro Tjahjono, Mulya Juarsa
Publikováno v:
AIP Conference Proceedings.
In order to develop the design of Reactor Cavity Cooling System (RCCS) from High Temperature Reactors (HTRs), Center for Nuclear Reactor Technology and Safety (PTKRN) has built an RCCS experimental facility aimed for supporting the development of met
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ae715a0d63e86db9de8e8be4d8b548cc
https://doi.org/10.1063/1.5135531
https://doi.org/10.1063/1.5135531
Autor:
Hendro Tjahjono, Anwar Budianto, Andi Sofrany Ekariansyah, Susyadi, Surip Widodo, Puradwi Ismu Wahyono
Publikováno v:
Journal of Physics: Conference Series. 1772:012035
The steam generator is an important component in any commercial nuclear power plants to deliver required steam from the reactor heat. Different with the steam generator design of PWR, other design in a small modular reactor (SMR) with smaller thermal
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b153db31e8804bd21fe7e3363c65a4a6
https://doi.org/10.1088/1742-6596/1772/1/012035
https://doi.org/10.1088/1742-6596/1772/1/012035
Autor:
M. Darwis Isnaeni, Andi Sofrany Ekariansyah, Surip Widodo, R. Andika Putra Dwijayanto, Sudarmono, Susyadi
Publikováno v:
International Journal on Advanced Science, Engineering and Information Technology. 10:1986
Since 2014, Indonesia's National Atomic Energy Agency (BATAN) has been launching a plan to construct a 10 MWt Experimental Power Reactor ( Reaktor Daya Eksperimental / RDE). The RDE design is based on the small-sized pebble-bed high-temperature gas-c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::85b38d511036f5f59f118a558e11a16f
https://doi.org/10.18517/ijaseit.10.5.10817
https://doi.org/10.18517/ijaseit.10.5.10817
Publikováno v:
Progress in Nuclear Energy. 125:103376
Probabilistic Safety Assessment (PSA) is an established approach to evaluate safety and performances of nuclear power plants (NPPs). It consists of coupled fault tree analysis (FTA) and event tree analysis (ETA). FTA is used to graphically model poss
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2b4d78581d568699898db6935bae460a
https://doi.org/10.1016/j.pnucene.2020.103376
https://doi.org/10.1016/j.pnucene.2020.103376
Autor:
Mukhsinun Hadi Kusuma, Hendro Tjahjono, Andi Sofrany Ekariansyah, Rahayu Kusumastuti, Mike Susmikanti
Publikováno v:
Journal of Physics: Conference Series. 1493:012004
Reaktor Daya Eksperimental (RDE) is a 10MWt small modular of High Temperature Gas-cooled Reactor (HTGR) with passive safety features. This reactor has a Reactor Cavity Cooling System (RCCS) to evacuate heat loss through reactor vessel in operation co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::251e3962021aeca087d9ef5fe7ec8403
https://doi.org/10.1088/1742-6596/1493/1/012004
https://doi.org/10.1088/1742-6596/1493/1/012004
Publikováno v:
Annals of Nuclear Energy. 85:1189-1199
A number of fuzzy fault tree analysis approaches, which integrate fuzzy concepts into the quantitative phase of conventional fault tree analysis, have been proposed to study reliabilities of engineering systems. Those new approaches apply expert judg
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d9cd32a9822d2be73bf0033b9b3a2df6
https://doi.org/10.1016/j.anucene.2015.08.002
https://doi.org/10.1016/j.anucene.2015.08.002