Results 101 to 110 of about 538 (156)

Sensitivity analysis of the LMT-006 benchmark experiments with OpenMC [PDF]

open access: yes
The LEU-MET-THERM-006 (Low Enriched Uranium fissile material, METal physical form, THERMal spectrum, LMT-006 for short) series of experiments was carried out in 1969-1970 by the CEA (Commissariat à l’Energie Atomique), France in the experimental ...
Ali, Nour
core  

A multidisciplinary framework from reactors to repositories for evaluating spent nuclear fuel from advanced reactors. [PDF]

open access: yesSci Rep
Wainwright HM   +6 more
europepmc   +1 more source

Estimation of minimum critical dimensions of process vessels handling Pu Nitrate Solution Using OpenMC

open access: yes, 2018
The exact values of minimum critical values (MCV) for Pu nitrate and Mixed U-Pu nitrate solutions are needed during the design and safe operations of any Fast Reactor Fuel Cycle Facilities.
Rawat, Ajay   +3 more
core  

Digital: accelerating the pathway. [PDF]

open access: yesPhilos Trans A Math Phys Eng Sci
Davis A   +6 more
europepmc   +1 more source

Neutronic characteristic analysis of the GAMA microreactor. [PDF]

open access: yesHeliyon
Harto AW   +7 more
europepmc   +1 more source

Long-term, sustainable solutions to radioactive waste management. [PDF]

open access: yesSci Rep
Kvashnina K   +5 more
europepmc   +1 more source

Analiza občutljivosti referenčnih testnih primerov LMT-006 z OpenMC

open access: yes
The LEU-MET-THERM-006 (Low Enriched Uranium fissile material, METal physical form, THERMal spectrum, LMT-006 for short) series of experiments was carried out in 1969-1970 by the CEA (Commissariat á l\u27Energie Atomique), France in the experimental ...
Elsaied, Nour Mohamed Ali Hussein
core  

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