The ENEA-Bologna Nuclear Data Group produced the VITJEF22.BOLIB (NEA-1699/01 ZZ VITJEF22.BOLIB) and MATJEF22.BOLIB (NEA-1740/0 I ZZ MATJEF22.BOLIB) fine-group coupled neutron and photon (199 n + 42 y) cross section libraries far nuclear fission applications, respectively in AMPX and MATXS format and based on the JEF-2.2 European nuclear data file. Both the libraries were produced from the same set of cross section files in GENDF format, generated with the NJOY-94.66 nucIear data processing system. The present libraries can be considered as European counterparts of the VITAMIN-B6 (DLC-0184 ZZ VITAMIN-B6) American library in AMPX format, based on the ENDF/B-VI Release 3 American nuclear data file. In fact they have the same general features and the same neutron and photon energy group structures as VITAMIN-B6. In particular, all these libraries are pseudo-problem-independent and based on the Bondarenko (f-factor) method far the treatment of neutron resonance self-shielding and temperature effects. Each ENEA-Bologna library contains a set of 133 nuclide cross section files processed at 4 temperatures (300 °K, 600 °K, 1000 °K and 2100 °K) and obtained far the most part with 6 to 8 values of the background cross section 0'0' Thermal scattering cross sections were processed at all the temperatures available in the JEF-2.2 thermal scattering law data file far 5 additional bound nuclides: H-I in light water, H-l in polyethylene, H-2 in heavy water, C in graphite and Be in beryllium meta!. Collapsed working libraries of self-shielded cross sections in the formats used by the deterministic transport codes of the DANTSYS and DOORS systems can be generated from VITJEF22.BOLIB and MATJEF22.BOLIB through, respectively, further problem-dependent data processing with the AMPX or SCAMPI nuclear data processing systems and with the TRANSX code. This work was performed in co-operation with specialists ofIPPE-Obninsk and with the constant scientific support of OECD/NEA Data Bank.

ENEA-BOLOGNA PRODUCTION AND TESTING OF JEF-2.2 MULTI-GROUP CROSS SECTION LIBRARIES FOR NUCLEAR FISSION APPLICATIONS

Pescarini, M.
2005

Abstract

The ENEA-Bologna Nuclear Data Group produced the VITJEF22.BOLIB (NEA-1699/01 ZZ VITJEF22.BOLIB) and MATJEF22.BOLIB (NEA-1740/0 I ZZ MATJEF22.BOLIB) fine-group coupled neutron and photon (199 n + 42 y) cross section libraries far nuclear fission applications, respectively in AMPX and MATXS format and based on the JEF-2.2 European nuclear data file. Both the libraries were produced from the same set of cross section files in GENDF format, generated with the NJOY-94.66 nucIear data processing system. The present libraries can be considered as European counterparts of the VITAMIN-B6 (DLC-0184 ZZ VITAMIN-B6) American library in AMPX format, based on the ENDF/B-VI Release 3 American nuclear data file. In fact they have the same general features and the same neutron and photon energy group structures as VITAMIN-B6. In particular, all these libraries are pseudo-problem-independent and based on the Bondarenko (f-factor) method far the treatment of neutron resonance self-shielding and temperature effects. Each ENEA-Bologna library contains a set of 133 nuclide cross section files processed at 4 temperatures (300 °K, 600 °K, 1000 °K and 2100 °K) and obtained far the most part with 6 to 8 values of the background cross section 0'0' Thermal scattering cross sections were processed at all the temperatures available in the JEF-2.2 thermal scattering law data file far 5 additional bound nuclides: H-I in light water, H-l in polyethylene, H-2 in heavy water, C in graphite and Be in beryllium meta!. Collapsed working libraries of self-shielded cross sections in the formats used by the deterministic transport codes of the DANTSYS and DOORS systems can be generated from VITJEF22.BOLIB and MATJEF22.BOLIB through, respectively, further problem-dependent data processing with the AMPX or SCAMPI nuclear data processing systems and with the TRANSX code. This work was performed in co-operation with specialists ofIPPE-Obninsk and with the constant scientific support of OECD/NEA Data Bank.
Lavori presentati a convegno o conferenza;Dati nucleari;Metodi deterministici per la neutronica
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/5224
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