Results 31 to 40 of about 171 (84)

Validation of the correlation-based aerosol model in the ISFRA sodium-cooled fast reactor safety analysis code

open access: yesNuclear Engineering and Technology, 2021
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]

open access: yes, 2020
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

open access: yesScience and Technology of Nuclear Installations, Volume 2018, Issue 1, 2018., 2018
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

Cross-sections for the ${^{27}\!\rm{Al}}(\gamma,\textit{x})^{24}\rm{Na}$ multiparticle reaction at $E_{\rm{\gamma max}}$ = 40 $\div$ 95 MeV

open access: yes, 2020
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]

open access: yes, 2015
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]

open access: yes, 2020
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]

open access: yes, 2020
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]

open access: yes, 2019
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]

open access: yes, 2018
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  

High-fidelity numerical investigation on structural integrity of SFR fuel cladding during design basis events

open access: yesNuclear Engineering and Technology
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

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