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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. [Pg.141]


See other pages where SUBGROUP CROSS-SECTION PROCESSING is mentioned: [Pg.21]    [Pg.21]    [Pg.13]    [Pg.21]    [Pg.128]    [Pg.226]    [Pg.142]    [Pg.70]    [Pg.87]   


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Processes crossed (cross

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