Results 41 to 50 of about 171 (84)

Phenomenological Study of Fuel Relocation Behavior and Formation of Debris Bed in Metal-fueled Sodium-cooled Fast Reactor [PDF]

, 2019
Department of Nuclear EngineeringMetallic fuel has been proposed as one of fuel types in sodium-cooled fast reactor (SFR). The metallic fuel has advantages in terms of safety issues. Especially, it has been known that severe accident for metal-fueled SFR
Heo, Hyo
core  

LES of the upper plenum of the liquid metal fast reactor under the forced flow conditions [PDF]

A Large Eddy Simulation (LES) of the upper plenum of the E-SCAPE (European SCAled Pool Experiment) facility under the normal operations has been conducted to gain deeper insights into the thermal hydraulics phenomena in liquid metal fast reactors (LMFRs).
Falcone, M., He, S., Saxena, A.
core   +1 more source

Applicability analysis of induction bending process to P91 piping of PGSFR by high-temperature creep tests

Nuclear Engineering and Technology
This study evaluated the high-temperature creep structural integrity of P91 induction-bent piping for Prototype Gen-IV Sodium-cooled Fast Reactors (PGSFR) through specimen creep tests and bent pipe structural creep test alongside inelastic analysis ...
Tae-Won Na, Dong-Gi Song, Nak-Hyun Kim, Chang-Gyu Park, Junehyung Kim, Jong-Bum Kim   +5 more
doaj   +1 more source

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

, 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  

Development Status and Plan of Metal Fuel of Integrated Fast Reactor [PDF]

Metal fuel has high breeding ratio, simple post-processing procedures, good safety, convenient disposal of long-lived actinides, and can be integrated into integrated fast reactor nuclear power plant, making it be an ideal choice for the fuel of fast ...
FENG Wei, LIU Yizhe, REN Yuanyuan, YANG Yong, ZHOU Peide
core   +1 more source

Research Progress on Ferritic/Martensitic Steels for Integrated Fast Reactor Fuel Cladding [PDF]

 The integrated fast reactors use metallic fuel， with fuel cladding operating at temperatures ranging from 350 ℃ to 630 ℃ and a service lifespan exceeding 50 000 hours.
Feng　Wei, Guan　Songyuan, Li　Junhong, Shan　Pengzhan, Xing　Weiwei, Hao　Xianchao, Liang　Tian, Ma　Yingche
core   +1 more source

A validation study of the SLTHEN code for hexagonal assemblies of wire-wrapped pins using liquid metal heating experiments

Nuclear Engineering and Technology
This paper presents a validation study of the subchannel analysis code SLTHEN used for the core thermal-hydraulic design of the Prototype Gen-IV sodium-cooled fast reactor (PGSFR).
Sun Rock Choi, Junkyu Han, Huee-Youl Ye, Jonggan Hong, Won Sik Yang   +4 more
doaj   +1 more source

Développement d’un modèle de transferts couplés pour l’aide à la conception et à la conduite des systèmes de purification du sodium des réacteurs à neutrons rapides [PDF]

, 2013
Les pièges froids sont des systèmes de purification du fluide caloporteur sodium indispensables au bon fonctionnement des réacteurs à neutrons rapides.
Khatcheressian, Nayiri
core   +3 more sources

The Statesman, v. 49, i. 10 [PDF]

, 2005
v. 49, i.
Stony Brook University
core   +1 more source

Research Progress in Key Thermal-hydraulic Issue of Sodium-cooled Fast Reactor [PDF]

Sodium-cooled fast reactors are considered the preferred reactor type for fourth generation nuclear energy systems due to their high thermal efficiency, high fuel utilization efficiency, inherent safety, and unique advantages of achieving a closed fuel ...
YANG Hongyi1, XUE Xiuli1, , , ZHOU Zhiwei1, LIN Chao1, LI Hongrui2, GAO Xinzhao1, YU Xintai1, MA Xiao1, XIAO Yubai1, LUO Rui2
core   +1 more source