Abstract
The present version of the nuclear data library International Reactor Dosimetry File IRDF-90 was compiled using mainly ENDF/B-VI data. In this library resonance region covariance information can be found that has not been processed. According to the philosophy of the algorithms included in the relevant cross section processing codes of the Neutron Metrology File NMF-90 of the Nuclear Data Section of the International Atomic Energy Agency, the library should contain only a single file for all the covariance information for each reaction. Therefore a computer code has been developed and used to process these data. The algorithm of the code is presented, some computational problems are mentioned, and the results of the calculations are discussed.
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