Cooling Period Calculation of Evolutionary Power Reactor Spent Fuel for Dry Management Safety
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چکیده
منابع مشابه
shielding and criticality safety analyses for spent fuel transportation cask in tehran research reactor
in this research, shielding and criticality safety calculations carried out for interim storage and transportation cask in the tehran research reactor. such dual purpose cask is being designed to the spent fuel elements of research reactors. the monte carlo mcnp5 code calculation was utilized for the criticality safety analysis and origen2.1code was used for shielding calculation. according to ...
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ژورنال
عنوان ژورنال: Nuclear and Radiation Safety
سال: 2016
ISSN: 2073-6231
DOI: 10.32918/nrs.2016.2(70).04