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Keyword [Code Development]
Result: 1 - 12 | Page: 1 of 1
1. Water Reactor Mox Fuel Performance Analysis And Program Development
2. Thermal-hydraulics Design And Safety Analysis Of A100MWth Small Natural Circulation Lead Cooled Fast Reactor SNCLFR-100
3. Research On The Key Methods Of Evaluation, Processing And Application Of Important Nuclear Data For Reactor And Code Development
4. 3D Transient Analysis Method And Code Development Of Fissile Solutions Criticality Accident
5. Development Of Transient Two-phase Thermal-hydraulic Code Base On Two-fluid Model
6. Thermal-hydraulic Safety Analysis Of Primary Cooling System For Small Modular Natural Circulation LFR SNCLFR-100
7. Development Of A Transient Analysis Program For Molten Salt Reactor
8. Development Of Subchannel Analysis Code For Lead Cooled Fast Reactor Subassembly
9. Investigation On Transient Heat Transfer Characteristic In Pressure Vessel Lower Head In Advanced Water Cooled Nuclear Reactors During Severe Accident
10. A process for identifying, characterizing, and incorporating risk concepts into performance-based building and fire regulation development
11. The Extension And Validation Of The Msr System Code,TREND
12. Research On Subchannel Analysis Method Of Lead-based Fast Reactor Fuel Assembly With Wire Spacers For CiADS
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