Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization
نویسندگان
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 Data Sheets
سال: 2015
ISSN: 0090-3752
DOI: 10.1016/j.nds.2014.12.016