Results 41 to 50 of about 128 (71)

Development of In-Service Inspection Techniques for PGSFR

open access: yesTransactions of the Korean Society of Pressure Vessels and Piping, 2016
Hoe Woong Kim   +6 more
openaire   +2 more sources

Magnetohydrodynaaminen pumppaus sekä sen mahdolliset sovellukset energiateollisuudessa

open access: yes, 2019
Työssä tarkastellaan kirjallisuudesta MHD-pumppausilmiön toimintaperiaatteita sekä selvittämään, minkätyyppisiä menetelmään perustuvia teknisiä konsepteja on käsitelty tai tutkittu.
Pesonen, Jussi
core  

Teaching Sodium Fast Reactors in CEA [PDF]

open access: yes, 2018
International audienceAmong the Fast Neutron Reactor Systems, the SFR has the most comprehensive technological basis as result of the experience gained from worldwide operation of several experimental, prototype, and commercial size reactors since the ...
Latgé, C., Gicquel, L., Beauchamp, F.
core   +1 more source

Analysis of the Efficiency of Electromagnetic Pump for Sodium Thermohydraulic Test according to Cooling Condition

open access: yes, 2017
The efficiency of electromagnetic pump with a mass flow rate of 20 kg/s and a developed pressure of 4 bar for sodium thermohydraulic test is analyzed in the both forced and natural cooling conditions.
Kwak, Jaesik, Kim, Hee Reyoung
core  

Characteristics Analysis of an Electromagnetic Pump for the Active Safety-grade Decay Heat Removal System in the Prototype Gen-IV Sodium-cooled Fast Reactor

open access: yes, 2018
Active Safety-grade Decay Heat Removal System (ADHRS) of Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR) releases heat from the primary system to the atmosphere of the final heat sink. An electromagnetic pump which is used in the ADHRS is considered
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core  

Expression of dicistronic transcriptional units in transgenic tobacco. [PDF]

open access: yesMol Cell Biol, 1989
Angenon G   +6 more
europepmc   +1 more source

?????????????????? ????????? ?????? ?????? ???????????? ?????? ?????? ????????? ????????? ????????? ?????? ?????? [PDF]

open access: yes, 2019
Department of Nuclear EngineeringAfter Fukushima accident (All of the core cooling systems and emergency power generator are deactivated because of the tsunami) in 2011, researchers started to focus the nuclear power plant accident research on the core ...
Moon, Sungbo
core  

Evaluation of High Temperature Structural Integrity of Intermediate Heat Exchanger in a Steady State Condition for PGSFR

open access: yesTransactions of the Korean Society of Pressure Vessels and Piping, 2016
Seong-Hyeon Lee   +2 more
openaire   +1 more source

Structural design and integrity evaluations for reactor vessel of PGSFR sodium-cooled fast reactor

open access: yesTransactions of the Korean Society of Pressure Vessels and Piping, 2016
Gyeong Hoi Koo, Sung Kyun Kim
openaire   +2 more sources

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