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eBook
Annals of Nuclear Energy, ISSN 0306-4549, 04/2018, Volume 114, pp. 427 - 436
With the prominent features of different U-Pu fuel compositions, the MOX-fueled fast spectrum metal-cooled reactors have been of increasing interest for recent... 
Code-to-code verification | Sodium void reactivity effect | Stainless steel reflector | SuperMC | BFS-62-3A | SYSTEM | SFR CORES | FACILITY | VALIDATION | CODES | NUCLEAR SCIENCE & TECHNOLOGY | BENCHMARK | SERPENT | VERIFICATION | Nuclear energy | Nuclear reactors | Steel, Stainless | Analysis | Radiation
Journal Article
Applied Thermal Engineering, ISSN 1359-4311, 07/2018, Volume 139, p. 264
Shroud tube is a porous protective covering over the Control Safety Rod Driving Mechanism assembly vertically submerged just below the free-surface of liquid... 
Liquid sodium | Performance evaluation | Design parameters | White light | Eccentricity | Gas entrainment | Variations | Nuclear engineering | Radial flow | Froude number | Nuclear safety | Flow generated vibrations | Pore size | Reactors | Fast breeder | Control rods | Porosity | Laser applications | Breeder reactors
Journal Article
International Journal of Energy Research, ISSN 0363-907X, 05/2017, Volume 41, Issue 6, pp. 854 - 866
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 2010, Volume 240, Issue 5, pp. 1195 - 1217
Sodium cooled fast reactors have been developed in France for nearly 50 years with successively Rapsodie, Phenix and Superphenix plants. Thermal hydraulic... 
CRITERIA | SUBASSEMBLY HEAT-TRANSFER | FAST BREEDER-REACTORS | NUCLEAR SCIENCE & TECHNOLOGY | NATURAL CIRCULATION | FUEL | FRICTION FACTORS | FLOW | STRATIFICATION | GAS ENTRAINMENT | EXCHANGER | Sodium | Computational fluid dynamics | Hydraulics | Fluid flow | Nuclear reactor components | Nuclear engineering | Nuclear power generation | Nuclear reactors
Journal Article
Nuclear Technology, ISSN 0029-5450, 02/2015, Volume 189, Issue 2, pp. 143 - 151
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 12/2019, Volume 355, p. 110347
An argon gas cover layer is usually used in Sodium-cooled Fast Reactors (SFR) above the pool of sodium to prevent leakage of air into the vessel getting in... 
Numerical simulation | Cover gas | Natural convection | Droplet-laden flow | Sodium aerosol | Sodium-cooled Fast Reactor
Journal Article
Nuclear Inst. and Methods in Physics Research, A, ISSN 0168-9002, 07/2017, Volume 860, pp. 6 - 12
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 05/2019, Volume 346, pp. 1 - 9
Within the framework of the Generation IV Sodium-cooled Fast Reactors R&D program at CEA, a low sodium void worth core concept has been developed. In this... 
ULOF | CFV | Mitigation devices | SIMMER-V PV | CORE | NUCLEAR SCIENCE & TECHNOLOGY | SIMMER-IV | Nuclear reactors | Research & development--R&D | Principal point | Discharge | Sodium cooled reactors | Mitigation | Flow simulation | Nuclear fuels | Sodium | Reactors | Simulation | Mathematical analysis | Relocation | Fast nuclear reactors | Accidents
Journal Article
International Journal of Heat and Mass Transfer, ISSN 0017-9310, 08/2019, Volume 138, pp. 496 - 507
Journal Article
Nuclear Inst. and Methods in Physics Research, A, ISSN 0168-9002, 03/2017, Volume 848, pp. 109 - 113
Journal Article
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