ENEEP Experimental Study of the TRIGA fuel characteristics (IA-1)

All day
7 February 2022 11 February 2022

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.

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