Events Calendar

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.

The aim of the course is to provide experimental opportunity for PhD students of nuclear engineering or physics to perform various experiments that may be used for the verification of certain calculations.

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.

The aim of the course is to provide experimental opportunity for PhD students of nuclear engineering or physics to perform various experiments that may be used for the verification of certain calculations.

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.

The aim of the course is to provide experimental opportunity for PhD students of nuclear engineering or physics to perform various experiments that may be used for the verification of certain calculations.

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.

The aim of the course is to provide experimental opportunity for PhD students of nuclear engineering or physics to perform various experiments that may be used for the verification of certain calculations.

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.

The aim of the course is to provide experimental opportunity for PhD students of nuclear engineering or physics to perform various experiments that may be used for the verification of certain calculations.