Zobrazeno 1 - 10
of 33
pro vyhledávání: '"Hendro Tjahjono"'
Publikováno v:
Business and Finance Journal, Vol 2, Iss 1 (2017)
The aim of the study was to analyze and determine the influence of leadership and communication, on employee motivation and performance at Satuan Polisi Pamong Praja Kota Surabaya. Branch, as many as 100 persons. Sampling technique samples (Slovin) d
Externí odkaz:
https://doaj.org/article/da269518a9f646709053659947848b6d
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:
Hendro Tjahjono, null Giarno, Ainur Rosidi, Dedy Haryanto, G. Bambang Heru, Andi Sofrany Ekaryansyah, Mulya Juarsa, Muksinun Hadi Kusuma
Publikováno v:
THE 4TH INTERNATIONAL CONFERENCE ON NUCLEAR ENERGY TECHNOLOGIES AND SCIENCES (ICoNETS) 2021.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::89bf1f9dc60d3cd5691bf458316f0ca3
https://doi.org/10.1063/5.0095691
https://doi.org/10.1063/5.0095691
Autor:
Mario Hadinata Prasetio, Hanny Anggraini, Hendro Tjahjono, Aditya Bintang Pramadana, Aulia Akbari, Mutiara Madyanova, Rinie Mekarsari, Andri Akbarizal, Prianto Setiawan
Publikováno v:
Day 3 Thu, October 14, 2021.
This paper describes the evolution of the hydraulic fracturing approach and design in the Alpha reservoir over the past years. Alpha reservoir in XYZ field is a laminated sandstone reservoir with low permeability in the range of 20 to 140 md at a dep
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8c2501d57e47bb7ef1a60d364bcf4485
https://doi.org/10.2118/205703-ms
https://doi.org/10.2118/205703-ms
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:
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:
Tri Dasa Mega, Vol 19, Iss 2, Pp 59-70 (2017)
A postulated loss of coolant accident (LOCA) shall be analyzed to assure the safety of a research reactor. The analysis of such accident could be performed using best estimate thermal-hydraulic codes, such as RELAP5. This study focuses on analysis of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::30f37066f2ef667b703ad8e3b3a3c1ff
http://jurnal.batan.go.id/index.php/tridam/article/view/3279
http://jurnal.batan.go.id/index.php/tridam/article/view/3279
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
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
Publikováno v:
Journal of Physics: Conference Series. 1772:012037
RDE is designed based on HTGR technologies; it has an active, passive and inherent safety system. Defence in depth philosophy is conducted. The heat transferred from the reactor vessel to the structure of the containment is equipment in the RDE has a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::95fa82b6ec6fba2e6efbfd6982218fde
https://doi.org/10.1088/1742-6596/1772/1/012037
https://doi.org/10.1088/1742-6596/1772/1/012037