Criticality calculations for the spent fuel storage pools for Etrr_1 and Etrr_2 reactors

• Autorzy: Aziz M. , Andrzejewski K.
• Języki publikacji: EN

Abstrakty

EN

A criticality analysis of two spent fuel storage pools for Etrr_1 and Etrr_2 research reactors was performed. The multiplication factor for the pools was calculated as a function of relevant lattice physics parameters. Monte Carlo code MCNP-4A code was used in the criticality calculations. The results were compared with those given by CITATION code and the results obtained formerly during the design phase of the pools [9] with the MONK 6.3 code. Safety of the pools was confirmed.

Słowa kluczowe

EN

criticality safety; research reactors

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2000
• Tom: Vol. 45, nr 2
• Strony: 141--144
• Opis fizyczny: Bibliogr. 9 poz., rys.

Twórcy

autor

Aziz M.

• Nuclear Safety Centre, 3 Ahmed Alzomer Str., Nasr City, Cairo, Egypt

autor

Andrzejewski K.

• Institute of Atomic Energy, Nuclear Safety Analysis Group, 05-400 Otwock-Świerk, Poland, Tel.: [phone], Fax: [phone]