Zobrazeno 1 - 10
of 29
pro vyhledávání: '"D.T. Sony Tjahyani"'
Autor:
D.T. Sony Tjahyani
Publikováno v:
Atom Indonesia, Vol 40, Iss 2, Pp 49-56 (2014)
The Westinghouse AP1000 is a new design nuclear power plant which has implemented the concept of passive system. Even though a passive system may be more reliable than an active one, the possibility of the passive system to fail still exists. In line
Externí odkaz:
https://doaj.org/article/84e11c347b7c41f0a1d39167f8ad0d62
Publikováno v:
Annals of Nuclear Energy. 110:234-243
Fuzzy probability – based fault tree analysis (FPFTA) has been recently developed and proposed to deal with the limitations of conventional fault tree analysis. In FPFTA, reliabilities of basic events, intermediate events and top event are characte
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1da58b6069267030066f78941af0cb68
https://doi.org/10.1016/j.anucene.2017.06.023
https://doi.org/10.1016/j.anucene.2017.06.023
Publikováno v:
AIP Conference Proceedings.
The fundamental safety function of the power reactor is to control reactivity, to removal heat from the reactor, and confinement of radioactive material. The safety analysis is used to ensure that each parameter is fulfilled on the design and is done
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e6565ec664ca33121817352c2514f048
https://doi.org/10.1063/1.5135528
https://doi.org/10.1063/1.5135528
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:
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
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
Publikováno v:
Annals of Nuclear Energy. 111:716-717
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::355e711d311f09b8e4f4b5ada3114494
https://doi.org/10.1016/j.anucene.2017.05.043
https://doi.org/10.1016/j.anucene.2017.05.043
Publikováno v:
Journal of Physics: Conference Series. 1198:022070
The safety level of nuclear power plant can be evaluated by using the adequacy of defence in depth that is implemented in the design. The defence in depth is to fulfill requirements of the fundamental safety function, which are reactivity control, he
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::97bd38f048d882b0fd919d651f405420
https://doi.org/10.1088/1742-6596/1198/2/022070
https://doi.org/10.1088/1742-6596/1198/2/022070
Autor:
D.T. Sony Tjahyani
Publikováno v:
KnE Energy. 1
In safety analysis, one of important parameters is core damage as this occasion can cause fission products to release. In that regard, all possible sequences afterward must be analyzed in order to ensure that all events have been considered, because
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::72551e3353cfecd7a74037410179ee0a
https://doi.org/10.18502/ken.v1i1.474
https://doi.org/10.18502/ken.v1i1.474
Publikováno v:
Journal of Physics: Conference Series. 962:012021
The need for large-scale experimental facilities to investigate the phenomenon of natural circulation flow rate becomes a necessity in the development of nuclear reactor safety management. The FASSIP-01 loop has been built to determine the natural ci
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cc4eba3fd2ebf6797fc50f5f309864e5
https://doi.org/10.1088/1742-6596/962/1/012021
https://doi.org/10.1088/1742-6596/962/1/012021