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Keyword [MCNP]
Result: 61 - 80 | Page: 4 of 5
61. Computer Simulation Of Proton Shielding And Radiation Damage In CdZnTe
62. Validation Of Reactor Criticality And Shielding Based On OpenMC
63. The Research Of The Spent Fuel Container Nuclear Criticality Safety Based On The MCNP Program
64. New Research On Neutron Spectrum Measurement
65. Monte Carlo Simulation Of Vacuum Compton Detector
66. Simulation And Calculation Of Neutron Imaging
67. Preliminary Study On The Measurement Of I-131 In Aerosol
68. Characterization Of ?1×1 Inch LaBr3(Ce)Scintilliator Detector Using MCNP Simulation And By Experiment
69. Research On Quantitative Method Of CARR Reactor Neutron Depth Profile
70. Nuclear Criticality Safety Calculating For Dissolution And Pulsed Extraction Column
71. Research On Sourceless Efficiency Calculation For Airborne Gamma-ray Spectrometer
72. The Design Of Reactor Power Monitor Based On 16N? Energy Spectrum Measurement
73. Neutron Irradiation Damage Analysis Of Several Structural Materials In Accelerator Driven Systems
74. Research Of N-? Time Correlation Measurement Based On EJ299-33A Plastic Scintillator
75. Research And Application Of New Scintillator Detector In Detection Limit Of Ground-Space Nuclear Radiation
76. Research On Key Technologies Of On-line Measurement Of Radioactive Soil Gamma Spectrum
77. Theoretical Research On The Direct Measurement Technology Of Tritium On The Material Surface Under ? Background Radiation
78. MCNP-based analysis on simulating small changes in system responses
79. Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP
80. Development of an adjoint Monte Carlo method for clinical prostate radiation treatment
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