Published 2005 | Version v1
Miscellaneous

ENEA-Bologna production and testing of JEF-2.2 multi-group cross section libraries for nuclear fission applications

  • 1. ENEA - Centro Ricerche - Ezio Clementel - Bologna (Italy)
  • 2. Institute of Physics and Power Engineering (IPPE), Kaluga Region (Russian Federation)

Description

The ENEA-Bologna Nuclear Data Group produced the VITJEF22.BOLIB (NEA-1699/01 ZZ VITJEF22.BOLIB) and MATJEF22.BOLIB (NEA-1740/01 ZZ MATJEF22.BOLIB) fine-group coupled neutron and photon (199 n + 42 γ) cross section libraries for 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 nuclear 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 for 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 for the most part with 6 to 8 values of the background cross section σ0. Thermal scattering cross sections were processed at all the temperatures available in the JEF-2.2 thermal scattering law data file for 5 additional bound nuclides: H-1 in light water, H-1 in polyethylene, H-2 in heavy water, C in graphite and Be in beryllium metal. 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. (authors)

Availability note (English)

Available from SFEN, 5 rue des Morillons, 75015 - Paris (France)

Additional details

Publishing Information

Publisher
SFEN
Imprint Place
Paris (France)
Imprint Pagination
25 p.
Report number
INIS-FR--09-0340

Conference

Title
M-C 2005- International topical meeting on mathematics and computation, supercomputing, reactor physics and nuclear and biological applications
Dates
12-15 Sep 2005
Place
Avignon (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
40054853
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BENCHMARKS; DATA COMPILATION; GROUP CONSTANTS; LIBRARIES; MULTIGROUP THEORY; NUCLEAR DATA COLLECTIONS; SPECIFICATIONS; VALIDATION; WEIGHTING FUNCTIONS
Descriptors DEC
CROSS SECTIONS; DATA; FUNCTIONS; INFORMATION; NEUTRON TRANSPORT THEORY; TESTING; TRANSPORT THEORY

Optional Information

Notes
39 refs.