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Proceedings of the Seventh ASTM-Euratom Symposium on Reactor Dosimetry
DE90 016528 The ENDF/B-VI cross-section evaluations for the four iron isotopes are summarized, emphasizing the major improvements over ENDF/B-V. The evaluations were mostly based on a preliminary file generated in 19S6 for natural iron that has been used for re-calculating several neutron-transport experiments, all of which showed improved agreement. These re-analyses, including those for pressure-vessel surveillance dosimetry, are also discussed.doi:10.1007/978-94-011-2781-3_40 fatcat:olehxahcgnfpdioxbvmtznyuj4