Fast Breeder Reactor
Acoustic monitoring of sodium boiling in a Liquid Metal Fast Breeder Reactor from autoregressive models
... (a) Raw signal spectrum (b) Filtered signal spectrum Figure 1: Comparison of the spectrum of raw signal and filtered signal for frequencies lower than 10 kHz. Water is suggested as potential substitute of liquid metal ...
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An accident probability analysis and design evaluation of the gas-cooled fast breeder reactor demonstration plant
... melt accident sequences allowed the determination of both the accident sequence probabilities and the sensitivity of these results to the reliability values of the [r] ...
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Status of the astrid sodium fast reactor project from conceptualdesign to basic design phase
... Mitsubishi Fast Breeder Reactor System (MFBR), AREVA and CEA, contribution, of ASTRID Design activities increased significantly during the year 2016 from three Task Sheets to ...
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Experimental qualification of rotatable plug seals for Sodium Fast Reactor on a large scale test stand
... the reactor vessel cover gas during the up/down vertical movements of the RP is ensure by the inflatable seal, while the massive double lips-seals (inverted-π shape) once compressed at the end of the translation ...
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Analytical developments for high precision isotope measurements on transmutation target in the phenix fast neutron reactor
... French fast neutron reactor Phénix is providing a collection of accurate information on the total capture integral cross sections of the principal heavy isotopes and some important fission ...
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A conservative approach to account for used fast-neutron reactor blankets in criticality-safety studies
... This study focuses on the radial and axial blankets of the French Sodium Fast Reactor, PHENIX. As illustrated in Fig.2, two rings of radial blankets (fertile assemblies) surround the fissile internal cores ...
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Characterization, simulation and improvement of spacer pads mechanical behaviour for sodium fast reactor fuel subassemblies
... ABSTRACT CEA is currently working on a new prototype of Sodium cooled Fast Reactor, ASTRID, which must demonstrate strong safety level. Spacer pads, which are small bosses stamped through faces of the ...
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Biomass fast pyrolysis in a drop tube reactor for bio oil production: Experiments and modeling
... In the present work, our aim is to improve comprehension of entrained flow fast pyrolysis of biomass using both experimental and modeling approaches. The experiments are performed in a lab scale drop tube ...
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Characterization, simulation and improvement of spacer pads mechanical behaviour for sodium fast reactor fuel subassemblies
... Optimization process Design parameters Results Conclusions Outline | PAGE 2 Introduction Spacer pads Historical overview Objectives.. Finite element model construction and val[r] ...
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Influence of particle size, reactor temperature and gas phase reactions on fast pyrolysis of beech wood
... tube reactor (DTR) was used to study the pyrolysis of particles between 350 and 800 µm, and a horizontal tubular reactor (HTR) was used to complete the study with larger particles (800 µm – 6mm) and to ...
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Analyses of experiments in the JOYO fast reactor using the ERANOS and JNC code systems
... In this paper, the study has been applied to the analysis of the JOYO MK-I core. Since it is a power reactor, measurements performed such as the burnup-characteristics complement those of critical facilities and ...
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Modeling and analysis of molten fuel vaporization and expansion for a sodium fast reactor severe accident
... 2. Modeling 2.1. Main assumptions The molten fuel studied is composed by uranium and plutonium oxides. A non-modeled nuclear power excursion is assumed to initiate the fuel melting down and superheating. The vessel’s ...
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Multi-objective optimization of sub-assemblies design towards static mechanical equilibrium of sodium-cooled fast reactor core
... Figure 3. View of the sub-assemblies array of a natural restrained CFV core. CALCULATION OF CORE STATIC MECHANICAL EQUILIBRIUM The HARMONIE V2 code has been developed to calculate static equilibrium conditions in the ...
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Design of passive decay heat removal system for the lead cooled flexible conversion ratio fast reactor
... The surface area of the perforated plate was added to the calculation of hydraulic diameter, and radiation heat transfer between the perforated plate and both side[r] ...
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Conceptual design of a lead-bismuth cooled fast reactor with in-vessel direct-contact steam generation
... The feasibility of a lead-bismuth (Pb-Bi) cooled fast reactor that eliminates the need for steam generators and coolant pumps was explored. The working steam is gen[r] ...
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Teaching Sodium Fast Reactor Technology and Operation for the Present and Future Generations of SFR Users
... sodium fast reactors, carried out respectively in the French Sodium and Liquid Metal School (ESML) created in 1975 and located in France (at the CEA Cadarache Research Centre), in the Fast Reactor ...
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Postvaccinal reovirus infection with high mortality in breeder chicks
... SUMMARY A broiler breeder flock was subcutaneously vaccinated at the hatchery with a live avian orthoreovirus (ARV) vaccine against viral arthritis. Chicks began to die at three days of age and post-mortem ...
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The significant collaboration of japan and france on the design of astrid sodium fast reactor since 2014
... This paper aims at a brief overview of involvement of JAEA/MHI–MFBR in the ASTRID design studies through these Design Task Sheets, covering in particular at the early beginning the design of an active decay heat removal ...
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3d simulation in the pleiades software environment for sodium fast reactor fuel pin behavior under irradiation
... various models used to assess fuel behaviour under irradiation. Among these improvements one concerns the closure of the pellet-to-cladding gap which controls the fuel maximal temperature at the beginning of ...
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A 2D/1D algorithm for effective cross sections generation in fast reactor neutronic transport calculations
... [4] N. Z. Cho, G. S. Lee, and C. J. Park, “A fusion technique of 2D/1D methods for three- dimensional whole-core transport calculations,” Proc. Korean Nuclear Society (2002). [5] D. Schneider, F. Dolci, F. Gabriel, J. ...
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