Results 31 to 40 of about 128 (71)

ICONE23-1331 RANS BASED CFD METHODOLOGY AND CHALLENGE IN MODELING REAL SCALE 217-PIN WIRE-WRAPPED FUEL ASSEMBLY OF KAERI PGSFR

open access: yesThe Proceedings of the International Conference on Nuclear Engineering (ICONE), 2015
Jeong, Jae-Ho   +4 more
openaire   +2 more sources

High-fidelity numerical investigation on structural integrity of SFR fuel cladding during design basis events

open access: yesNuclear Engineering and Technology
A high-fidelity numerical analysis methodology was proposed for evaluating the fuel rod cladding integrity of a Prototype Gen IV Sodium Fast Reactor (PGSFR) during normal operation and Design basis events (DBEs).
Seo-Yoon Choi   +3 more
doaj   +1 more source

Risk mitigation strategy by Passive IN-core Cooling system for advanced nuclear reactors

open access: yes, 2018
After the Fukushima accident, the installation of passive safety systems for nuclear power plants becomes necessary as protection against external power failures.
In Cheol Bang   +9 more
core   +1 more source

The Comparative Analysis of Rectangular- and Helical-type DC Electromagnetic Pump for ADHRS in PGSFR

open access: yes, 2017
A DC electromagnetic pump with rectangular- and helical-type was optimally analyzed for the active heat decay removal system (ADHRS) in prototype GenIV sodium fast reactor (PGSFR). The direct current (DC) electromagnetic pump was used to circulate liquid
Kim, Hee Reyoung, Lee, Geunhyeong
core  

Velocity Distribution Analysis of an Electromagnetic Pump for the Active Safety-grade Decay Heat Removal System in the PGSFR

open access: yes, 2017
An electromagnetic pump is analyzed using numerical analysis method for the verification of characteristics An electromagnetic pump is considered for the generation of sodium flow satisfying easy control of flow rate, because it is operated without ...
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core  

Nuclear waste from small modular reactors. [PDF]

open access: yesProc Natl Acad Sci U S A, 2022
Krall LM, Macfarlane AM, Ewing RC.
europepmc   +1 more source

Evaluation of the MCNP6 Code for SFR Shielding Analysis

open access: yes, 2018
The Prototype Generation-IV Sodium-cooled Fast Reactor (PGSFR) design is being conducted by KAERI with support of Korean government. Shielding analysis, which ensures the radiation safety of the core design, is challenging for the Monte Carlo modeling ...
Jeong, Sanggeol   +8 more
core  

Design Variable Analysis of ALIP for the Circulation of Sodium in the IHTS of PGSFR

open access: yes, 2015
The design variables of the Annular Linear Induction electromagnetic Pump (ALIP) were analyzed for the circulation of liquid sodium in the Intermediate Heat Transport System (IHTS) of the Prototype Generation-IV Sodium cooled Fast Reactor (PGSFR) of 150 ...
Kwak, Jaesik, Kim, Hee Reyoung
core  

Analysis of an electromagnetic pump for sodium thermohydraulic test in the prototype Gen-IV sodium-cooled fast reactor

open access: yes, 2017
The characteristics of an electromagnetic pump which is used for the circulation of sodium coolant in the Prototype Generation IV Sodium-cooled Fast Reactor (PGSFR) is analyzed.
Kim, Hee Reyoung, Kwak, J
core  

Slow desiccation leads to high-frequency shoot recovery from transformed somatic embryos of cotton (Gossypium hirsutum L. cv. Coker 310 FR)

open access: yes, 2003
In Agrobacterium-mediated genetic transformation of cotton ( Gossypium hirsutum L. cv. Coker 310FR) the frequency at which somatic embryos were converted to plantlets was significantly improved by subjecting the embryos to slow physical desiccation.
Oinam, G. S.   +5 more
core   +1 more source

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