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[PDF] Top 20 Progress in the design of the ASTRID nuclear island

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Progress in the design of the ASTRID nuclear island

Progress in the design of the ASTRID nuclear island

... inside the primary vessel whereas they were outside the primary vessel in PX; both concepts have provided satisfactory ...results. The main requirements for ASTRID are to try to limit ... Voir le document complet

9

ASTRID Nuclear Island design update in French-Japanese joint team development of Decay Heat Removal systems

ASTRID Nuclear Island design update in French-Japanese joint team development of Decay Heat Removal systems

... vessel in the reactor pit. Transfer of heat from primary sodium is based on radiating process of both main vessel and safety vessels (relying on steel ...Because of its location, RRC is ... Voir le document complet

7

Astrid project, from conceptual to basic design progress status

Astrid project, from conceptual to basic design progress status

... 5. The consolidation phase and beyond From November 2016 until the end of December 2017, the consolidation phase of the Basic Design will take ...an ASTRID ... Voir le document complet

11

Status of astrid architecture in starting of basic design phase

Status of astrid architecture in starting of basic design phase

... for the evacuation of the earthwork materials and the delivery of the voluminous equipment of the nuclear island during all the ...Because ... Voir le document complet

11

Status of the astrid sodium fast reactor project from conceptualdesign to basic design phase

Status of the astrid sodium fast reactor project from conceptualdesign to basic design phase

... end of December 2017, the consolidation phase of the Basic Design will take ...an ASTRID design file with the gas PCS comparable to that produced at the end ... Voir le document complet

8

ASTRID Nuclear Island design : advances in French-Japanese joint team development of Decay Heat Removal systems

ASTRID Nuclear Island design : advances in French-Japanese joint team development of Decay Heat Removal systems

... through the cold pool and quickly reaches the bottom of the ...illustrates the cooled sodium path leaving the RRA-DHX. Path starts at the top of the RRA-DHX ... Voir le document complet

7

conceptual design of astrid radial shielding sub-assemblies

conceptual design of astrid radial shielding sub-assemblies

... 9. Design of borated steel shielding S/A ...that the temperature reached in the borated steel block is 770°C while the pressure in the wrapper tube is ...10). ... Voir le document complet

9

Conceptual design of ASTRID radial shielding sub-assemblies

Conceptual design of ASTRID radial shielding sub-assemblies

... plug the micrometric pores of the vents and hinder pin ...considering the sub-millimetre cladding-pellet gap inside the ...that the sodium inside the Na-bonded absorber ... Voir le document complet

9

Conceptual design of ASTRID radial shielding sub-assemblies

Conceptual design of ASTRID radial shielding sub-assemblies

... first design, but was still significantly above the target ...increasing the distance between the core and the IHXs was not an option regarding the vessel size, it has been ... Voir le document complet

12

Recent progress in the optimal design of composite structures: industrial solution procedures on case studies

Recent progress in the optimal design of composite structures: industrial solution procedures on case studies

... used in this paper, depend- ing on the application. The selection of an efficient optimi- zation method depends on the problem to be ...when the problem includes a large number ... Voir le document complet

6

Nuclear reactors' construction costs: The role of lead-time, standardization and technological progress

Nuclear reactors' construction costs: The role of lead-time, standardization and technological progress

... provides the first comparative analysis of nuclear reactor construction costs in France and the United ...Studying the cost of nuclear power has often been a ... Voir le document complet

31

Plateau facility in support to ASTRID and the sfr program: an overview of the first mock-up of the ASTRID upper plenum, MICAS

Plateau facility in support to ASTRID and the sfr program: an overview of the first mock-up of the ASTRID upper plenum, MICAS

... injections in the mock-ups with different flow-rates and temperatures. The first mock-up tested on PLATEAU will be ...scale of the ASTRID internal vessel built in ... Voir le document complet

10

Recent progress on dense nuclear matter in skyrmion approaches

Recent progress on dense nuclear matter in skyrmion approaches

... on the contrast of the BPS approach to the current lore of nuclear physics is in order ...ingredients in the currently predominant attitude among ... Voir le document complet

25

Pre-conceptual design of ASTRID fuel sub-assemblies

Pre-conceptual design of ASTRID fuel sub-assemblies

... inside the S/A (section view) The lower part of the neutron shield comprises the 19- pin bundle equipped with flow equalisers, while the upper part comprises the ... Voir le document complet

10

Implementation of probabilistic assessments to support the ASTRID decay heat removal systems design process

Implementation of probabilistic assessments to support the ASTRID decay heat removal systems design process

... respect the 24-hours probabilistic ...Objectives of the dynamic approaches Dynamic approaches enable users to take into account not only the order of component failure but also ... Voir le document complet

10

Progress of the SPIRAL2 Project

Progress of the SPIRAL2 Project

... for the RIB part. TIS Production System For the production of the RIBs at the future ISOL facility SPIRAL 2 different production methods are being ...foreseen. The primary beams ... Voir le document complet

6

large electro-magnetic pump conceptual design for the astrid sodium-cooled fast reactor

large electro-magnetic pump conceptual design for the astrid sodium-cooled fast reactor

... Email of corresponding author: tetu.suzuki@toshiba.co.jp Abstract: Within the framework of the French Sodium Fast Reactor (SFR) prototype called ASTRID (Advance Sodium Technological ... Voir le document complet

7

Study of the Free Surface Flow in the MICAS Mock-Up in Support of the ASTRID SFR Program

Study of the Free Surface Flow in the MICAS Mock-Up in Support of the ASTRID SFR Program

... that the IHX4 and IHX3 exhibit the maximum occurrence ...Nevertheless, the air entrainment is not only depending on this factor; it is also correlated with the vortex ...but the bigger ... Voir le document complet

12

Progress of the LUNEX5 Project

Progress of the LUNEX5 Project

... PRESENTATION OF LUNEX5 In this context, LUNEX5 [26] proposes to develop a demonstrator for investigating the production of short, intense, and coherent pulses in the soft X-ray ... Voir le document complet

6

Overview on nuclear corrosion - Corrosion in the nuclear cycle

Overview on nuclear corrosion - Corrosion in the nuclear cycle

... for the deposit and dissemination of sci- entific research documents, whether they are pub- lished or ...not. The documents may come from teaching and research institutions in France or ... Voir le document complet

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