Radiation Problems : from Analytical to Monte-Carlo Solutions.

Intro
Radiation Problems: From Analytical to Monte-Carlo Solutions
Abstract
Basic Calculations of the Fluence Rate for Sources of Different Geometric Shapes
Basic Calculations of Ambient Dose Equivalent
Dose and Kerma Calculation for Photons in a Medium Composed of Interfaces
Calculation of the Ambient Dose Equivalent Rate in a Uniformly Contaminated Pipe
Calculation of the In-Depth Absorbed Dose for &
hx03B2
Spectra
Calculation of the Absorbed Dose Profile to Water for 170 MeV Protons
Neutron Kerma Calculation and Microdosimetric Spectrum Reconstruction with a Tissue Equivalent Proportional Counter
Gas-Filled Detector Operating in Ionization Chamber Mode for Photons and in Proportional Counter Mode for Neutrons
Calibration of an Ionization Chamber with a 60Co Source
Calculation of a Dose Rate in a LiF Pellet
Measurement of the Operational Quantity H'(0.07, 0) for a β Spectrum with an Extrapolation Chamber
Fast Monoenergetic Neutron Energy and Fluence Measurements with a Proton Recoil Telescope
Fast Monoenergetic Neutron Time of Flight Energy Measurement
Measurement of a Realistic Neutron Spectrum Using Bonner Spheres
Absorbed Dose Measurement in a Water Calorimeter for a 170 MeV Proton Beam Used in Proton Therapy
Calibration of a Neutron Survey Meter with a 252Cf Source
Shielding Calculation for an AmBe Neutron Source
Calculation of a 60Co Photon Source Ambient Dose Equivalent Rate Behind a 4 m Water Shielding
Radiological Shielding for an X-ray Generator
Evaluation of Ambient Dose Equivalent from Neutron Activation
Calculation of the Scattered Ambient Equivalent Dose Rate for an X-ray Generator Beam on a Water Phantom
Calculation of Radiological Shielding for a 20 MeV Electron Accelerator with an X-ray Conversion Target
Foreword
Acknowledgments.

Contents
Calculation of Radiometric and Dosimetric Quantities (Fluence, Kerma, Dose and Ambient Dose Equivalent)
Basic Calculations of the Fluence Rate for Sources of Different Geometric Shapes
Basic Calculations of Ambient Dose Equivalent
Dose and Kerma Calculation for Photons in a Medium Composed of Interfaces
Calculation of the Ambient Dose Equivalent Rate in a Uniformly Contaminated Pipe
Calculation of the in-Depth Absorbed Dose for &
hx03B2
Spectra
Calculation of the Absorbed Dose Profile to Water for 170 MeV Protons
Neutron Kerma Calculation and Microdosimetric Spectrum Reconstruction with a Tissue Equivalent Proportional Counter
Detection Principles, Detector Response to Reference Physical Quantities and Operational Dosimetric Quantities
Gas-Filled Detector Operating in Ionization Chamber Mode for Photons and in Proportional Counter Mode for Neutrons
Calibration of an Ionization Chamber with a 60Co Source
Calculation of a Dose Rate in a LiF Pellet
Measurement of the Operational Quantity H'(0.07,0) for a β Spectrum with an Extrapolation Chamber
Fast Monoenergetic Neutron Energy and Fluence Measurements with a Proton Recoil Telescope
Fast Monoenergetic Neutron Time of Flight Energy Measurement
Measurement of a Realistic Neutron Spectrum Using Bonner Spheres Spectrometer
Absorbed Dose Measurement in a Water Calorimeter for a 170 MeV Proton Beam Used in Proton Therapy
Calibration of a Neutron Survey Meter with a 252Cf Source
Shielding and Activation Calculations for Several Types of Devices (Radioactive Sources, X-ray Generators, Accelerators...)
Shielding Calculation for an AmBe Neutron Source
Calculation of a 60Co Photon Source Ambient Dose Equivalent Rate Behind a 4 m Water Shielding
Radiological Shielding for an X-ray Generator.

Evaluation of Ambient Dose Equivalent from Neutron Activation
Calculation of the Scattered Ambient Equivalent Dose Rate for an X-ray Generator Beam on a Water Phantom
Calculation of Radiological Shielding for an Electron Accelerator with an X-ray Conversion Target
References.