Abstract
The broad-group library BGL1000_B7 for neutron and gamma transport calculations in VVER-1000 internals, RPV and shielding was carried out on a base of fine-group library v7-200n47g from SCALE-6 system. The comparison of the library BGL1000_B7 with the library v7-200n47g and the library BGL1000 (the latter is using for VVER-1000 calculations) is demonstrated on several calculation and experimental tests.
Highlights
Cross section libraries BUGLE-96 [1] and BGL1000 [2] (47 neutron groups and 20 gamma groups) are used at present time for internals and pressure vessel dosimetry calculations of the VVER-1000 reactor types
The comparison of the library BGL1000_B7 with the library v7-200n47g and the library BGL1000 is demonstrated on several calculation and experimental tests
Those broad-group libraries were developed from fine-group library VITAMIN-B6 [3], which is based on ENDF/B-VI.3 evaluated data files
Summary
Cross section libraries BUGLE-96 [1] and BGL1000 [2] (47 neutron groups and 20 gamma groups) are used at present time for internals and pressure vessel dosimetry calculations of the VVER-1000 reactor types. Those broad-group libraries were developed from fine-group library VITAMIN-B6 [3], which is based on ENDF/B-VI. evaluated data files. The spectra averaged for different materials and temperatures were prepared using the obtained fine-group solution Those spectra were used in the SCALE-6 system for the generation of broad-group cross-sections from fine-group ones.
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