SUBGROUP CROSS-SECTION PROCESSING

The most widely used computer code to process evaluated nuclear data into group cross section libraries is the NJOY code [4.2]. In addition, a code may be needed to convert the data produced by NJOY into the form required by a particular code scheme. For the treatment of resonance shielding auxiliary codes can be required to produce the appropriate parameters (e.g. the CALENDF code [4.6] for subgroup parameter calculations). There are other processing codes, such as GRUCON [4.3], AMPX [4.4] and ETOE [4.5] which are used mainly in the nuclear research centres where they were originated. 

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