Identyfikatory
Warianty tytułu
Języki publikacji
Abstrakty
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
Czasopismo
Rocznik
Tom
Strony
141--144
Opis fizyczny
Bibliogr. 9 poz., rys.
Twórcy
autor
- Nuclear Safety Centre, 3 Ahmed Alzomer Str., Nasr City, Cairo, Egypt
autor
- Institute of Atomic Energy, Nuclear Safety Analysis Group, 05-400 Otwock-Świerk, Poland, Tel.: +4822/ 7180021, Fax: +4822/ 7793888
Bibliografia
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-BUJ5-0004-0099