In this individual course the TRIGA fuel characteristics are studied in detail with different experiments.

• Measurement of the thermal neutron flux density in the reactor core.
• Measurement of the Control rod calibration based on the released reactivity and the corresponding reactor period.
• Determination of the reactivity value of uranium fuel- and graphite elements in different core positions.
• Determination of the core excess reactivity combined with the determination of the temperature coefficient of the reactivity
• Study of different pulses of the reactor, combine the released reactivity with the corresponding energy and power of the pulse.