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8
Neutronic_and_thermal_hydraulic_analysis_for_production_of_fission_Mo99_Pakistan[1].pdf
TechnicalNoteNeutronic thermalhydraulic analysis productionoffission molybdenum-99 PakistanResearch R
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75
improving natural uranium utilization by using thorium in low moderation pwrs - a preliminary neutronic scoping study (749.52kb).pdf
improving natural uranium utilization by using thorium in low moderation pwrs - a preliminary neutronic scoping study (749.52kb)
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202
Laser Inertial Fusion-based Energy Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear.pdf
Laser Inertial Fusion-based Energy Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear
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51
osmose an experimental program for improving neutronic predictions of advanced nuclear fuels. (1.06mb).pdf
osmose an experimental program for improving neutronic predictions of advanced nuclear fuels. (1.06mb)
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202
Laser Inertial Fusion-based Energy Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System.pdf
Laser Inertial Fusion-based Energy Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System
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86
a neutronic analysis of tru recycling in pwrs loaded with mox-ue fuel (mox with u-235 enriched u support) (694.18kb).pdf
a neutronic analysis of tru recycling in pwrs loaded with mox-ue fuel (mox with u-235 enriched u support) (694.18kb)
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58
neutronic benchmarks for the utilization of mixed-oxide fuel joint u.s.russian progress report for fiscal year 1997 - volume 4, part 2--saxton plutonium program critical experiments (1...pdf
neutronic benchmarks for the utilization of mixed-oxide fuel joint u.s.russian progress report for fiscal year 1997 - volume 4, part 2--saxton plutonium program critical experiments (1.03mb)
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