Vitenea-J is a coupled multigroup cross section library in the standard VITAMIN-J energy group structure (175 n - 42 γ) in AMPX format produced by ENEA-FIS-MET Bologna for nuclear fusion applications. It is based on nuclear data from the general purpose Fusion Evaluated Nuclear Data Library (FENDL/E-2.0) and ENDF-B/VI. The library contains 75 nuclides. Seventy nuclides were processed at four temperatures (300 0K, 600 0K, 900 0K, 1500 0K) at ten values for the background cross section σ0. Thermal scattering cross sections were processed at three temperatures available in the ENDF-B/VI thermal scattering law data file for four additional bound nuclides: H-1 in water, C in graphite, Be in beryllium metal and oxide. The temperatures 296 0K, 600 0K, 1200 0K for C in graphite, Be in Be-metal and BeO and 296 0K, 500 0K, 1000 0K for H in H2O were chosen respectively. The material characterized by MAT=900 has been added in the library. It contains the ANSI standard neutron/gamma flux to dose rate factors, in the 175n and 42γ group structure, to be used for dose rate calculations. From Vitenea-J library it is possible to produce, via modules of the AMPX-77 or Scale-4.4a Processing Systems, working libraries (even collapsed) of self-shielded cross sections to be used by transport codes that need multigroup cross section data in AMPX or FIDO format.

VITENEA-J, AMPX 175-N,42-gamma multigroup X-sect. library for nuclear fusion applications

CAMBI, GILIO
2004

Abstract

Vitenea-J is a coupled multigroup cross section library in the standard VITAMIN-J energy group structure (175 n - 42 γ) in AMPX format produced by ENEA-FIS-MET Bologna for nuclear fusion applications. It is based on nuclear data from the general purpose Fusion Evaluated Nuclear Data Library (FENDL/E-2.0) and ENDF-B/VI. The library contains 75 nuclides. Seventy nuclides were processed at four temperatures (300 0K, 600 0K, 900 0K, 1500 0K) at ten values for the background cross section σ0. Thermal scattering cross sections were processed at three temperatures available in the ENDF-B/VI thermal scattering law data file for four additional bound nuclides: H-1 in water, C in graphite, Be in beryllium metal and oxide. The temperatures 296 0K, 600 0K, 1200 0K for C in graphite, Be in Be-metal and BeO and 296 0K, 500 0K, 1000 0K for H in H2O were chosen respectively. The material characterized by MAT=900 has been added in the library. It contains the ANSI standard neutron/gamma flux to dose rate factors, in the 175n and 42γ group structure, to be used for dose rate calculations. From Vitenea-J library it is possible to produce, via modules of the AMPX-77 or Scale-4.4a Processing Systems, working libraries (even collapsed) of self-shielded cross sections to be used by transport codes that need multigroup cross section data in AMPX or FIDO format.
M. Frisoni; D.G. Cepraga; G. Cambi
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11585/6162
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