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Keyword [MCNP code]
Result: 1 - 8 | Page: 1 of 1
1.
Research Of Effective Neutron Multiplication Factor And Neutron Flux Distribution For Accelerator Driven Sub-Critical System On DF-3 Facility
2.
Simulation Design On Beam Shaping Assembly For Neutron Radiography Based D-D And D-T Neutron Source
3.
Core Physics Design Calculation Of Minitype Fast Reactor By MCNP Code
4.
The Associated Particle Method On The Neutron Yield Measurement And The M-C Simulation Study On The N/γ Field For D-D/D-T Neutron Generator
5.
Co-60 Irradiation Facility Of Dose Distributions For The Calculation And Measurement
6.
Study On Physical Characteristics Of The New MOX Fuel Assembly In Supercritical Water Cooled Reactor
7.
Simulation Study On A Minitype Reference Radiation With Monte Carlo Method And Its Application
8.
Development of an adjoint Monte Carlo method for clinical prostate radiation treatment
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