Results 31 to 40 of about 171 (84)
ISFRA (Integrated SFR Analysis Program for PSA) computer program has been developed for simulating the response of the PGSFR pool design with metal fuel during a severe accident.
Churl Yoon +4 more
doaj +1 more source
Experimental validation of simulating natural circulation of liquid metal using water [PDF]
Liquid metal-cooled reactors use various passive safety systems driven by natural circulation. Investigating these safety systems experimentally is more advantageous by using a simulant.
Bang, In Cheol +2 more
core +1 more source
Preliminary Selection of Device Materials to Locally Transform Thermal into SFR Neutron Spectrum
The safe introduction of Generation IV (Gen IV) reactor concepts into operation will require extensive testing of their components. This must be performed under neutronic conditions representative of those expected to prevail inside the new reactor cores when in operation.
N. Chrysanthopoulou +6 more
wiley +1 more source
The bremsstrahlung flux-averaged cross-sections $\langle{\sigma(E_{\rm{\gamma max}})}\rangle$ and the cross-sections per equivalent photon $\langle{\sigma(E_{\rm{\gamma max}})_{\rm{Q}}}\rangle$ were measured for the photonuclear multiparticle reaction $^{
Deiev, O. S. +3 more
core +1 more source
Liquid metal cooled fast reactors [PDF]
Fast spectrum reactors offer the capability for a better utilization of uranium resources. They are in principle capable to produce (“breed”) but also to transmute (“burn”) fissile materials either by means in a critical or in case of lead alloys even in
Hering, W. +3 more
core +2 more sources
Study on natural circulation of the reactor pool under RVACS operation using fluid to fluid model simulating experiment [PDF]
Department of Nuclear EngineeringPassive safety becomes more and more important under station black out situation like Fukushima, providing trustworthy countermeasure for the accident.
Lee, Min Ho
core
Numerical Evaluation of Thermal Striping in MLNG Tiga Regenerative Piping [PDF]
Temperature fluctuations or known as thermal striping able to develop cyclic thermal stresses resulting in thermal fatigue. This can lead to unexpected failure of pipe material.
ZULKIFLI, MUHAMMAD AFIQ IKHWAN
core
Numerical Simulation of Fluid-Structure Interaction during the Expansion Phase in Sodium Cooled Fast Reactors [PDF]
Im Falle einer schweren Störung können natriumgekühlte, schnelle Reaktoren (Sodium Cooled Fast Reactors, (SFR)s) eine teilweise Zerstörung des Reaktorkerns erfahren. Die veränderte Zu- sammensetzung von spaltbarem Material nach einem solchen Hypothetical
Hartig, Maximilian
core +2 more sources
Teaching Sodium Fast Reactors in CEA [PDF]
International audienceAmong the Fast Neutron Reactor Systems, the SFR has the most comprehensive technological basis as result of the experience gained from worldwide operation of several experimental, prototype, and commercial size reactors since the ...
Beauchamp, F., Gicquel, L., Latgé, C.
core
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

