Development of Fission Source Acceleration Method for Slow Convergence in Criticality Analyses by Using Matrix Eigenvector Applicable to Spent Fuel Transport Cask with Axial Burnup Profile

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ژورنال

عنوان ژورنال: Journal of Nuclear Science and Technology

سال: 2003

ISSN: 0022-3131,1881-1248

DOI: 10.1080/18811248.2003.9715377