Abstract
The ENEA-Bologna Nuclear Data Group produced the VITJEFF32.BOLIB multi-group coupled neutron/photon (199 n + 42 γ) cross section library in AMPX format, based on the OECD-NEA Data Bank JEFF-3.2 evaluated nuclear data library. VITJEFF32.BOLIB was conceived for nuclear fission applications as European counterpart of the ORNL VITAMIN-B7 similar library (ENDF/B-VII.0 data). VITJEFF32.BOLIB has the same neutron and photon energy group structure as the former ORNL VITAMIN-B6 reference library (ENDF/B-VI.3 data) and was produced using similar data processing methodologies, based on the LANL NJOY-2012.53 nuclear data processing system for the generation of the nuclide cross section data files in GENDF format. Then the ENEA-Bologna 2007 Revision of the ORNL SCAMPI nuclear data processing system was used for the conversion into the AMPX format. VITJEFF32.BOLIB contains processed cross section data files for 190 nuclides, obtained through the Bondarenko (f-factor) method for the treatment of neutron resonance self-shielding and temperature effects. Collapsed working libraries of self-shielded cross sections in FIDO-ANISN format, used by the deterministic transport codes of the ORNL DOORS system, can be generated from VITJEFF32.BOLIB through the cited SCAMPI version. This paper describes the methodology and specifications of the data processing performed and presents some results of the VITJEFF32.BOLIB validation.
Highlights
In the last two decades, the three-dimensional (3D) deterministic discrete ordinates (SN) transport codes using group-wise cross section libraries extended their practical simulation capability to an enlarged variety of nuclear systems with different neutron spectra and high geometrical complexity
Various factors concurred to determine the increased flexibility and convenience of the 3D SN codes: 1) the impressive increased performance of modern computers, 2) innovative fine-group pseudo-problem-independent cross section libraries with upscatter cross sections, 3) new ancillary pre/post-processor systems of programs dedicated to 2D and 3D deterministic transport codes and 4) no need to justify, as in the case of the Monte Carlo codes, the statistics adopted with respect to the requirements of the nuclear safety authorities
Examples of broad-group working libraries for LWR shielding and pressure vessel dosimetry applications are: BUGLE-96 [1] derived from VITAMIN-B6, BUGLE-B7 [3] from VITAMIN-B7 and BUGJEFF311.BOLIB [16] from VITJEFF311.BOLIB
Summary
In the last two decades, the three-dimensional (3D) deterministic discrete ordinates (SN) transport codes using group-wise cross section libraries extended their practical simulation capability to an enlarged variety of nuclear systems with different neutron spectra and high geometrical complexity In particular they increased their competitiveness with respect to the 3D Monte Carlo codes in radiation shielding and damage safety analyses in nuclear fission reactor applications. With the recent availability of the cited ancillary pre/post-processor systems, the 3D SN codes increased dramatically their geometrical simulation capability and this induced an increased interest to give more availability of updated group-wise cross section libraries This is justified both in terms of the previously cited fine-group coupled n/J pseudoproblem-independent mother libraries and broad-group. In the present paper in particular the generation of the VITJEFF32.BOLIB [18] fine-group coupled neutron and photon (199 n + 42 J) cross section library in AMPX format for nuclear fission applications, based on the OECD-NEA Data Bank JEFF-3.2 most updated evaluated nuclear data library, is described
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