Three-dimensional (3D) fixed source transport calculations in Cartesian (X,Y,Z) geometry for the Iron-88 single-material (Fe) neutron shielding benchmark experiment were performed using the TORT-3.2 discrete ordinates (SN) transport code. The ENEA-Bologna BUGJEFF311.BOLIB (JEFF-3.1.1 data) and BUGENDF70.BOLIB (ENDF/B-VII.0 data) broad-group coupled (47 n + 20 γ) working cross section libraries in FIDO-ANISN format and the similar ORNL BUGLE-B7 (ENDF/B-VII.0 data) and BUGLE-96 (ENDF/B-VI.3 data) libraries, specifically conceived for LWR shielding and pressure vessel dosimetry applications, were alternatively used together with dosimeter cross sections, processed from the IAEA IRDF-2002 dosimetry file. The ENEA-Bologna codes ADEFTA-4.1 and BOT3P-5.3 were respectively employed for the calculation of the isotopic atomic densities and for the automatic generation of the spatial mesh grid of the geometrical model. The calculated reaction rates were compared with the corresponding experimental data, obtained using Au-197(n,γ)Au-198/Cd activation dosimeters and Rh-103(n,n')Rh-103m, In-115(n,n')In-115m, S-32(n,p)P-32 and Al-27(n,α)Na-24 threshold activation dosimeters. Given the total experimental uncertainties at 1σ, then the computational results presented exhibit good statistical consistency with the corresponding measurements except for the Al-27(n,α)Na-24 strongly overestimated results.

Iron-88 (Fe) Neutron Shielding Benchmark Experiment - Deterministic Analysis in Cartesian (X,Y,Z) Geometry Using the TORT-3.2 3D Transport Code and the BUGJEFF311.BOLIB, BUGENDF70.BOLIB, BUGLE-B7 and BUGLE-96 Cross Section Libraries

Orsi, Roberto;Pescarini, Massimo
2019-02-15

Abstract

Three-dimensional (3D) fixed source transport calculations in Cartesian (X,Y,Z) geometry for the Iron-88 single-material (Fe) neutron shielding benchmark experiment were performed using the TORT-3.2 discrete ordinates (SN) transport code. The ENEA-Bologna BUGJEFF311.BOLIB (JEFF-3.1.1 data) and BUGENDF70.BOLIB (ENDF/B-VII.0 data) broad-group coupled (47 n + 20 γ) working cross section libraries in FIDO-ANISN format and the similar ORNL BUGLE-B7 (ENDF/B-VII.0 data) and BUGLE-96 (ENDF/B-VI.3 data) libraries, specifically conceived for LWR shielding and pressure vessel dosimetry applications, were alternatively used together with dosimeter cross sections, processed from the IAEA IRDF-2002 dosimetry file. The ENEA-Bologna codes ADEFTA-4.1 and BOT3P-5.3 were respectively employed for the calculation of the isotopic atomic densities and for the automatic generation of the spatial mesh grid of the geometrical model. The calculated reaction rates were compared with the corresponding experimental data, obtained using Au-197(n,γ)Au-198/Cd activation dosimeters and Rh-103(n,n')Rh-103m, In-115(n,n')In-115m, S-32(n,p)P-32 and Al-27(n,α)Na-24 threshold activation dosimeters. Given the total experimental uncertainties at 1σ, then the computational results presented exhibit good statistical consistency with the corresponding measurements except for the Al-27(n,α)Na-24 strongly overestimated results.
Fisica nucleare;Fisica dei reattori nucleari;Dati nucleari;Rapporto tecnico
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/8094
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