Results 101 to 110 of about 538 (156)
Sensitivity analysis of the LMT-006 benchmark experiments with OpenMC [PDF]
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]
Wainwright HM +6 more
europepmc +1 more source
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
Non-uniform fuel distribution and thermo-mechanical analysis of a 1 MW thermal power micronuclear heat pipe reactor. [PDF]
Aziz U, Koreshi ZU, Khan H, Sheikh SR.
europepmc +1 more source
Digital: accelerating the pathway. [PDF]
Davis A +6 more
europepmc +1 more source
Neutronic characteristic analysis of the GAMA microreactor. [PDF]
Harto AW +7 more
europepmc +1 more source
Long-term, sustainable solutions to radioactive waste management. [PDF]
Kvashnina K +5 more
europepmc +1 more source
Extension of OpenMC for Fixed Source Transmutation Calculations [PDF]
openaire +1 more source
X-ray and γ-ray beam interstellar communication and implications for SETI. [PDF]
Beveridge L, Bruhaug G.
europepmc +1 more source
Analiza občutljivosti referenčnih testnih primerov LMT-006 z OpenMC
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

