The 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 were chosen for C in graphite, Be in Be-metal and BeO while 296 0K, 600 0K, 1200 0K for H in H2O. 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 which need multigroup cross section data in AMPX or FIDO format. This library is widely used by ENEA group in neutron/gamma transport as part of the SCALENEA-1 code sequence applied to safety assessment of fusion machines (ITER,SEAFP etc.)

Vitenea-J :a multigroup coupled (175 n - 42 γ) cross-section library in AMPX format for nuclear fusion applications

CAMBI, GILIO
2004

Abstract

The 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 were chosen for C in graphite, Be in Be-metal and BeO while 296 0K, 600 0K, 1200 0K for H in H2O. 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 which need multigroup cross section data in AMPX or FIDO format. This library is widely used by ENEA group in neutron/gamma transport as part of the SCALENEA-1 code sequence applied to safety assessment of fusion machines (ITER,SEAFP etc.)
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D.G. Cepraga; M. Frisoni; G. Cambi
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11585/5540
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