Radiation Physics and Engineering

A peer-reviewed journal published by K. N. Toosi University of Technology

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A B C D E F G H I J K L M N O P Q R S T U V W X Y Z ALL

C

  • Computational calculations ThO2 spent fuel assembly’s gamma dose rate dependency to burnup and cooling time [Volume 1, Issue 3, 2020, Pages 43-48]

F

  • Fast Neutron Conceptual design of a high-performance hybrid object for applications of the fast neutron irradiation in MTRs [Volume 1, Issue 4, 2020, Pages 65-76]

G

  • Gamma dose rate ThO2 spent fuel assembly’s gamma dose rate dependency to burnup and cooling time [Volume 1, Issue 3, 2020, Pages 43-48]

I

  • Irradiating Applications Conceptual design of a high-performance hybrid object for applications of the fast neutron irradiation in MTRs [Volume 1, Issue 4, 2020, Pages 65-76]

M

  • MCNPX2.6 code Calculation of neutronic and kinetic parameters of Isfahan Miniature Neutron Source Reactor using slope fit and perturbation methods [Volume 1, Issue 4, 2020, Pages 1-8]

  • MCNPX code ThO2 spent fuel assembly’s gamma dose rate dependency to burnup and cooling time [Volume 1, Issue 3, 2020, Pages 43-48]

  • MNSR Calculation of neutronic and kinetic parameters of Isfahan Miniature Neutron Source Reactor using slope fit and perturbation methods [Volume 1, Issue 4, 2020, Pages 1-8]

N

  • Neutronic and kinetic parameters Calculation of neutronic and kinetic parameters of Isfahan Miniature Neutron Source Reactor using slope fit and perturbation methods [Volume 1, Issue 4, 2020, Pages 1-8]

  • Neutron Spectrum Shift Conceptual design of a high-performance hybrid object for applications of the fast neutron irradiation in MTRs [Volume 1, Issue 4, 2020, Pages 65-76]

P

  • Perturbation Method Calculation of neutronic and kinetic parameters of Isfahan Miniature Neutron Source Reactor using slope fit and perturbation methods [Volume 1, Issue 4, 2020, Pages 1-8]

R

  • Research Reactor Conceptual design of a high-performance hybrid object for applications of the fast neutron irradiation in MTRs [Volume 1, Issue 4, 2020, Pages 65-76]

S

  • Slope fit method Calculation of neutronic and kinetic parameters of Isfahan Miniature Neutron Source Reactor using slope fit and perturbation methods [Volume 1, Issue 4, 2020, Pages 1-8]

T

  • Thorium spent fuel ThO2 spent fuel assembly’s gamma dose rate dependency to burnup and cooling time [Volume 1, Issue 3, 2020, Pages 43-48]

  • TRR Conceptual design of a high-performance hybrid object for applications of the fast neutron irradiation in MTRs [Volume 1, Issue 4, 2020, Pages 65-76]