Transport of Ionizing Radiation and Monte Carlo Method

Course guarantor:

Lecturer:

Tutor:

Supervisor:

Department of Dosimetry and Application of Ionizing Radiation

Synopsis:

Introduction to principles of Monte Carlo method and its use for radiation transport simulation, selected concepts of probability theory and mathematical statistics. Physical models of interaction of different types of radiation and their use for stochastic modeling of their substance transport. Model description concepts, geometric model layout, source term, scoring methods, and modeling of measured variables and parameters. Statistical evaluation of reliability of modeling results, variance reduction methods, program codes and tools for radiation transport modeling, MCNP program, its possibilities and use. Procedures for the practical use of the program for typical tasks in the field of dosimetry, application of ionizing radiation, detection and detection systems, radiation protection and medical applications.

Requirements:

Basic courses of matematics and statistics.

Basic knovledge of programming and computer literacy.

Advantade is course 18MOCA Monte Carlo Method.

Syllabus of lectures:

1. Introduction, basics of probability theory and mathematical statistics, random numbers

2. Physical principles of radiation transport modeling, database of cross-sections

3. Monte Carlo method, principles of stochastic methods

4. Methods of geometric description and material composition of the model

5. Simulation of indirectly ionizing radiation transport through matter (photons, neutrons)

6. Transport of charged particles, multiple scattering of electrons and condensed history

7. Statistical evaluation of reliability of modeling results (evaluation of precision/accuracy of results)

8. Programs and programming tools for modeling of radiation transport , MCNP

9. Methods of source term description, implementation in MCNP

10. Tallies, scoring methods, determination of model variables and parameters

11. Methods of variance reduction

12. Fundamentals of work with MCNP, demonstrations of solution in the alternative Fluka program

13. Exercise - application of the Monte Carlo method to typical tasks in the field of dosimetry, application of ionizing radiation, detection and detection systems, radiation protection and medical applications

Syllabus of tutorials:

1. Basics of MCNP

2. Procedures for model preparation (geometric and material description, source, tally, model parameters)

3. Detector response model, interpretation of results and errors, statistical evaluation

4. Calculation of the calibration factor

5. Methods of determination of dosimetric quantities, determination of dose

6. Application of variance reduction methods

7. Shield computations, medical beams, spatial distributions of simulated quantities (advanced tally types)

8. The use of repeated and lattice structures in the description of more complex geometric arrangements

Study Objective:

Knowledge:

Acquiring basic theoretical and practical knowledge about the Monte Carlo method and the possibilities of its use in the field of radiation transport simulation.

Skills:

Control of basic programming tools, preparation of simple models for practical applications in the fields of dosimetry, detectors, spectrometry, shielding and radiation protection and medical applications.

Study materials:

Key references:

[1] Lux, I., Koblinger, L.: Monte Carlo Particle Transport Methods- Neutron and Proton Calculations, ISBN 0-8493-6074-9, CRC Press, 1991.

Recommended references:

[2] Use of MCNP in Radiation Protection and Dosimetry, Edited by Gualdrini, G., Casalini, L., ENEA, ISBN 88-8286-000-1, Bologna - Italy, May 13-16 1996.

[3] MCNP 5/6/X Manuals

Media and tools:

computer lab

computer codes and SW/tools for radiation transport simulation

Note:

Further information:

behounek.fjfi.cvut.cz/

No time-table has been prepared for this course

The course is a part of the following study plans: