Extensive Revision of the Kernel-based PREVIEW Program and its Input Data

Tom Serén, Frej Wasastjerna

Research output: Contribution to journalArticleScientificpeer-review


The kernel-based PREVIEW program, which calculates fluences, fluence rates, reaction and damage rates, etc. at a few important out-of-core locations in the Loviisa VVER-440 reactors has been extensively revised. New location-specific dosimetry cross sections based on the newly released IRDF-2002 library have been developed. A few cross-section condensation codes are tried and compared. Generally the results are in good agreement. Small differences may be attributable to the use of single precision and to different representations of the weighting spectrum. Also, some codes use the basic ENDF-format data directly while others use processed data with reduced precision.
Original languageEnglish
Pages (from-to)1-6
JournalJournal of ASTM International
Issue number3
Publication statusPublished - 2006
MoE publication typeA1 Journal article-refereed


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