Reactor calculations

Completed undergraduate cycle. Knowledge acquired in courses of Physics of fission reactors Radiation and reactor physics.
Positive result from midterm exam (or final written exam) is necessary to enter the oral exam.

Nuclear data: Nuclear reaction cross sections, differential and double-differential cross sections; experimental, evaluated, processed; averaging over energy groups and space; multi-group approximation; nuclear data libraries for applications; covariance matrices of cross section uncertainty.
Computational methods: Cellular calculation, energy group condensation and homogenization; fuel element calculation; global reactor core calculation; basics of Monte Carlo method; sensitivity analysis and uncertainties.

1. P. Obložinsky (ur.), A. Gandini(ur.) Proceedings of the Workshop Nuclear Reaction Data and Nuclear Reactors : Physics, design and safety. Singapore: World Scientific Publishing, 1999, str. 218-242 [COBISS-SI-ID 14520103]
2. R.J.J. Stammler, M.J. Abbate, Methods of Steady-State Reactor Physics in Nuclear Design, Academic Press, London, 1983.

Objectives: Basic understanding of the source and form of nuclear data used in calculation of particle transport in matter.
Competences: Overview and use of mathematical methods for particle transport computation in reactor calculations.

Knowledge and understanding:
Learning of and understanding different types of nuclear data; Knowledge of different computational methods in reactor calculations.
Application:
Knowledge on sources of nuclear data and their use in different phases of reactor calculations.
Reflection:

Different cases of nuclear and reactor physics use in practical application.
Transferable skills:
Acquired knowledge enables the listener to find suitable nuclear data for use in nuclear, reactor and radiology physics on world wide web in other international data libraries.

Lectures, homework, consultations, using computer to find data over world wide web.

Final written exam
oral exam
grading: 5 (fail), 6-10 (pass) (according to the Statute of UL)

Luka Snoj:
1. SNOJ, Luka, TRKOV, Andrej, RAVNIK, Matjaž, ŽEROVNIK, Gašper. Testing of cross section libraries on zirconium benchmarks. Ann. nucl. energy. [Print ed.], 2012, vol. 42, str. 71-79.
2. SNOJ, Luka, ŽEROVNIK, Gašper, TRKOV, Andrej. Computational analysis of irradiation facilities at the JSI TRIGA reactor. Appl. radiat. isotopes., 2012, vol. 70, str. 483-488.
3. JET EFDA Contributors, SNOJ, Luka, TRKOV, Andrej, LENGAR, Igor, POPOVICHEV, Sergei, CONROY, S., SYME, B. Calculations to support JET neutron yield calibration : Neutron scattering in source holder. Fusion eng. des.., 2012, iss. 11, vol. 87, str. 1846-1852.]
4. SNOJ, Luka, TRKOV, Andrej, JAĆIMOVIĆ, Radojko, ROGAN, Petra, ŽEROVNIK, Gašper, RAVNIK, Matjaž. Analysis of neutron flux distribution for the validation of the computational methods for the optimization of research reactor utilization. Appl. radiat. isotopes. [Print ed.], 2011, vol. 69, issue 1, str. 136-141, doi: 10.1016/j.apradiso.2010.08.019.
5. SNOJ, Luka, KROMAR, Marjan, ŽEROVNIK, Gašper, RAVNIK, Matjaž. Advanced methods in teaching reactor physics. Nucl. Eng. Des.. [Print ed.], 2011, vol. 241, issue 4, str. 1008-1012, doi: 10.1016/j.nucengdes.2010.02.040.

Robert Jeraj:
6. Ravnik, M. and Jeraj, R., Research reactor benchmarks, Nucl Sci Eng 132(9), 2003, 145-152.
7. Jeraj, R., Zagar, T., and Ravnik, M., Monte Carlo simulation of the TRIGA Mark II benchmark experiment with burned fuel, Nucl Technol 137(3), 2001, 169-79.
8. Jeraj, R., Glumac, B., and Maucec, M., Monte Carlo simulation of the TRIGA Mark II benchmark experiment, Nucl Technol 120, 1997, 179-187.