Font Size: a A A
Keyword [Neutron transport]
Result: 1 - 20 | Page: 1 of 2
1. Research On Direct Simulation Method For Neutron Continuous-energy Spacial Kinetics
2. Investigation On Method Of Characteristics For Solving Neutron Transport Equation And Embedded Assembly Homogenization Method
3. Simulation Design On Beam Shaping Assembly For Neutron Radiography Based D-D And D-T Neutron Source
4. The Analysis Of Influencing Factors In Neutron Transport Problem Calculation Using MCNP
5. Study On Neutron Transport Performance Of Reactor Core Based On UH X 2 2
6. Investigation On GPU-Parallel Accelerated Neutron Transport Method Of Characteristics For Hexagonal Cores And Multiple Nulcides Resonance Interference Effect
7. Development Of R-Z Dimensional Neutron Transport Code Based On Discrete Ordinates Method
8. Multigroup Neutron Transport Monte Carlo Calculation
9. Activation Calculation And Analysis For CFETR Magnet System
10. The Application Of Adaptive Discontinuous Finite Element Method In Neutron Transport Problem
11. Research On Three-dimensional High-efficiency Neutron Transport Method Based On HEPS_N
12. Research On Real Time Cross Sections Generation In Monte Carlo Neutron Transport With Wide Energy Region
13. Lattice Boltzmann Modeling Of Neutron Transport Process And Its Complex Mesh Technique
14. Research On The High-efficiency Even-parity Discrete Ordinates Method Based On Finite Volume Method
15. Research On Calculation Of Reactor Fine Power Distribution Based On MOC
16. Development Of The System Safety Analysis Code For Critical And External Neutron Driven Sub-critical Fast-spectrum Reactor
17. Simulation of reactor pulses in fast burst and externally driven nuclear assemblies
18. Complex problems arising in the collision probability theory for neutron transport
19. Neutron transport with the method of characteristics for 3-D full core boiling water reactor applications
20. Improved analysis of bias in Monte Carlo criticality safety (Neutron transport)
  <<First  <Prev  Next>  Last>>  Jump to