1,720,985 research outputs found
Updating of the Libraries Included in the ANITA-2000 Code Package on the Basis of the JEFF-3.1.1 Radioactive Decay Data Library
Full text linkANITA-2000 is a code package for the activation characterization of materials exposed to neutron irradiation released by ENEA at OECD-NEADB (NEA-1638). The package contains: a) the activation code ANITA-4M, based on the original code developed at CEC JRC Ispra, able to compute the radioactive inventory of a material exposed to neutron irradiation, continuous or stepwise, b) two activation cross section libraries, c) the decay data library (file “fl1”) containing the quantities describing the decay properties of unstable nuclides and d) the library (file “fl2”) containing the gamma ray spectra emitted by the radioactive nuclei in the ORNL-SCALE 18- energy group structure. The data contained in the “fl1” and “fl2” libraries of the ANITA-2000 code package are based on the evaluated data library FENDL/D-2.0. Taking into account a specific interest of ENEA and Ansaldo Nucleare, the ANITA-2000 “fl1” and “fl2” libraries were updated on the basis of the JEFF-3.1.1 Radioactive Decay Data Library. This work required the setting up of a series of proper interface codes in order to process and convert the JEFF-3.1.1 evaluated decay data (in ENDF-6 standard format) into the format required by ANITA-4M code. A preliminary validation of the new libraries has been performed through the comparison of the ANITA-4M calculations against measurements of electron-photon decay heat and activity of neutron activated materials from FNG (Frascati Neutron Generator) experiment
Production of the ANITA-NC system able to treat material activation due to neutral or charged particles
No full textANITA-NC (Analysis of Neutron Induced Transmutation and Activation – Neutral and Charged) is an inventory system developed in ENEA-Bologna, capable of modelling the material activation induced by several neutral and charged projectiles (neutron, proton, alpha, deuteron and gamma).
It is suitable to be applied to the study of the irradiation effects on materials in facilities like the International Fusion Materials Irradiation Facility (IFMIF) and, more recently, the DEMO Oriented Neutron Source (DONES), in which a considerable amount of neutrons with energies above 20 MeV is produced. In fact, in these facilities the deuterons will themselves cause activation, particularly in the accelerator structure and in the lithium target.
ANITA-NC includes and extends the capabilities of the ANITA-IEAF code, able to assess the activation of materials exposed to neutrons with energies up to 55 MeV. ANITA-IEAF was released by ENEA to OECD-NEADB where is in free distribution (NEA-1638). In this report the main characteristics of ANITA-NC are given. An example of calculation for both deuteron and proton activation performed by ANITA-NC are also shown. The results are compared with the FISPACT-II predictions
ANITA-IEAF intermediate energy neutron activation package: updating and validation of the decay and cross section data libraries
No full textANITA-IEAF is an activation package (code and libraries) developed in the past in ENEA-Bologna in order to assess the activation of materials exposed to neutrons with energies greater than 20 MeV. It is suitable to be applied to the study of the irradiation effects on materials in facilities like the International Fusion Materials Irradiation Facility (IFMIF) and, more recently, the DEMO Oriented Neutron Source (DONES), in which a considerable amount of neutrons with energies above 20 MeV is produced. The original package contained: a) the activation code ANITA-IEAF, able to manage the large amount of reactions with threshold higher than 20 MeV and up to 150 MeV, b) the activation cross section library based on the Intermediate Energy Activation File IEAF-2001, c) the Decay, Hazard and Clearance data library (file fl1) containing the quantities describing the decay properties of unstable nuclides and d) the Gamma library (file fl2) containing the gamma ray spectra emitted by the radioactive nuclei. The ANITA-IEAF package has been recently updated. The data contained in the fl1 and fl2 files are actually based on the JEFF-3.1.1 Radioactive Decay Data Library. The updated code uses the EAF-2010 group-wise neutron activation cross section library “eaf_n_gxs_211_flt_20010” in the VITAMIN-J+ (211 energy groups structure) up to 55 MeV . In this report the validation effort related to the comparison between the code predictions and the activity measurements obtained from the Karlsruhe Isochronous Cyclotron is presented
ANITA-IEAF: an intermediate energy neutron activation system
No full textANITA-IEAF is an activation package (code and libraries) developed in ENEA-Bologna in order to assess the activation of materials exposed to neutrons with energies up to 55 MeV. It is suitable to be applied to the study of the irradiation effects on materials in facilities like the International Fusion Materials Irradiation Facility (IFMIF) and, more recently, the DEMO Oriented Neutron Source (DONES), in which a considerable amount of neutrons with energies above 20 MeV is produced. The package provides: a) the activation code ANITA-IEAF, b) the activation cross section library, file “eaf2010_lib”, based on the EAF-2010 group-wise neutron activation cross section library “eaf_n_gxs_211_flt_20010” in the VITAMIN-J+ (211 energy group structure) up to 55 MeV, c) the Decay, Hazard and Clearance data library (file “fl1”) containing the quantities describing the decay properties of unstable nuclides and d) the Gamma library (file “fl2”) containing the gamma ray spectra emitted by the radioactive nuclei. The data contained in the fl1 and fl2 files are based on the JEFF-3.1.1 Radioactive Decay Data Library. Three test cases (both input and output files) are included in the code package. In this report the main characteristics of the code and the libraries, together with the description of the input and output files, are given. It can be used as the ANITA-IEAF “user’s manual”. The validation effort related to the comparison between the code predictions and the activity measurements obtained from the Karlsruhe Isochronous Cyclotron is also presented
Validation of the updated decay data libraries of the ANITA-2000 activation code package on experimental data produced by FNS-JAERI
No full textANITA-2000 is a code package for the activation characterization of materials exposed to neutron irradiation released by ENEA to OECD-NEADB (NEA-1638) and ORNL-RSICC (CCC-693). The package contains: a) the activation code ANITA-4M, based on the original code developed at CEC JRC Ispra, able to compute the radioactive inventory of a material exposed to neutron irradiation, continuous or stepwise, b) two activation cross section libraries, c) the decay data library (file “fl1”) containing the quantities describing the decay properties of unstable nuclides and d) the library (file “fl2”) containing the gamma ray spectra emitted by the radioactive nuclei in the ORNL-SCALE 18- energy group structure. The data contained in the “fl1” and “fl2” libraries of the ANITA-2000 code package have been recently updated on the basis of the JEFF-3.1.1 Radioactive Decay Data Library. The present report summarises the results of the validation of the updated decay data libraries, using the ANITA-4M code, through the comparison with the decay heat experimental results related to the material samples irradiated in the 14 MeV neutron flux of the Fusion Neutronics Source (FNS), JAERI (Japan Atomic Energy Research Institute, actually JAEA), Tokai, Japan
VITJEFF32.BOLIB - An ENEA-Bologna Fine-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format Based on JEFF-3.2 Data
No full textThe ENEA-Bologna Nuclear Data Group produced the VITJEFF32.BOLIB multi-group coupled (199 n + 42 γ) cross section library in AMPX format, based on the OECD-NEA Data Bank JEFF-3.2 evaluated nuclear data library. The generation of the VITJEFF32.BOLIB library for nuclear fission applications was conceived as an European counterpart of the ORNL VITAMIN-B7 library based on ENDF/B-VII.0 data. The present library has the same neutron/photon energy group structure and general features as the former ORNL VITAMIN-B6 reference library and was produced using similar data processing methodologies, based on the NJOY-2012.53 and SCAMPI nuclear data processing systems. VITJEFF32.BOLIB is a pseudo-problem-independent library based on the Bondarenko (f-factor) method for the treatment of neutron resonance self-shielding and temperature effects. The library contains 184 standard (not bound) nuclides singularly processed at 4 temperatures (300, 600, 1000 and 2100 K) and at 11 background cross sections. Thermal scattering cross sections were processed at all the temperatures available in the JEFF-3.2 thermal scattering law data file for 6 additional bound nuclides: H-1 in light water, H-1 in polyethylene, H-1 in zirconium hydride, H-2 in heavy water, C in graphite and Be in beryllium metal. From VITJEFF32.BOLIB it is possible to generate, through the ENEA-Bologna 2007 Revision of SCAMPI, collapsed working libraries of self-shielded cross sections in AMPX or FIDO-ANISN format for LWR applications
VITJEFF32.BOLIB - A JEFF-3.2 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications
No full textThe ENEA-Bologna Nuclear Data Group produced the VITJEFF32.BOLIB multi-group coupled (199 n + 42 γ) cross section library in AMPX format, based on the OECD-NEA Data Bank JEFF-3.2 evaluated nuclear data library. The generation of the VITJEFF32.BOLIB library for nuclear fission applications was conceived as an European counterpart of the ORNL VITAMIN-B7 library based on ENDF/B-VII.0 data. The present library has the same neutron/photon energy group structure and general features as the former ORNL VITAMIN-B6 reference library and was produced using similar data processing methodologies, based on the NJOY-2012.53 and SCAMPI nuclear data processing systems. VITJEFF32.BOLIB is a pseudo-problem-independent library based on the Bondarenko (f-factor) method for the treatment of neutron resonance self-shielding and temperature effects. The library contains 184 standard (not bound) nuclides singularly processed at 4 temperatures (300, 600, 1000 and 2100 K) and at 12 background cross sections. Thermal scattering cross sections were processed at all the temperatures available in the JEFF-3.2 thermal scattering law data file for 6 additional bound nuclides: H-1 in light water, H-1 in polyethylene, H-1 in zirconium hydride, H-2 in heavy water, C in graphite and Be in beryllium metal. From VITJEFF32.BOLIB it is possible to generate, through the ENEA-Bologna 2007 Revision of SCAMPI, collapsed working libraries of self-shielded cross sections in AMPX or FIDO-ANISN format for LWR applications
PCA-Replica (H2O/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 and BUGLE-96 Cross Section Libraries
No full textThree-dimensional (3D) fixed source transport calculations in Cartesian (X,Y,Z) geometry for the PCA-Replica 12/13 water/iron (H2O/Fe) engineering neutron shielding benchmark experiment were performed using the TORT-3.2 discrete ordinates (SN) 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 ) working cross section libraries in FIDO-ANISN format together with the similar ORNL BUGLE-96 (ENDF/B-VI.3 data) library, 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 programs 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 dosimetric and spectral results were compared with the corresponding experimental data, respectively obtained with threshold activation dosimeters (Rh-103(n,n')Rh-103m, In-115(n,n')In-115m and S-32(n,p)P-32), spherical hydrogen-filled proportional counters (type SP-2) and a spherical organic liquid (NE213) scintillator. Given the total experimental uncertainties at 1σ, then the computational results presented exhibit very good statistical consistency with the corresponding measurements. PCA-Replica, reproducing the ex-core radial geometry of a PWR, is particularly fit to test the cited working libraries since it was specifically conceived to check calculated fast neutron fluxes in a PWR mild steel pressure vessel simulator
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-96 Cross Section Libraries on the PCA-Replica (Water/Iron) Neutron Shielding Benchmark Experiment
No full textThree-dimensional (3D) fixed source transport calculations in Cartesian (X,Y,Z) geometry for the PCA-Replica 12/13 water/iron (H2O/Fe) engineering neutron shielding benchmark experiment were performed with the TORT-3.2 discrete ordinates (SN) 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 together with the similar ORNL BUGLE-96 (ENDF/B-VI.3 data) library, 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 programs 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 integral and spectral results were compared with the corresponding experimental data, respectively obtained with threshold activation dosimeters (Rh-103(n,n')Rh-103m, In-115(n,n')In-115m and S-32(n,p)P-32), spherical hydrogen-filled proportional counters (type SP-2) and a spherical organic liquid (NE213) scintillator. PCA-Replica, reproducing the ex-core geometry of a PWR, is particularly fit to test the cited working libraries since it was specifically conceived to check calculated fast neutron fluxes in a PWR mild steel pressure vessel simulator
Three-Dimensional (X,Y,Z) Deterministic Analysis of the PCA-Replica Neutron Shielding Benchmark Experiment Using the TORT-3.2 Code and Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry
Full text linkThe PCA-Replica 12/13 (H2O/Fe) neutron shielding benchmark experiment was analysed using the ORNL TORT-3.2 3D SN code. PCA-Replica, specifically conceived to test the accuracy of nuclear data and transport codes employed in LWR shielding and radiation damage calculations, reproduces a PWR ex-core radial geometry with alternate layers of water and steel including a PWR pressure vessel simulator. Three broad-group coupled neutron/photon working cross section libraries in FIDO-ANISN format with the same energy group structure (47 n + 20 γ) and based on different nuclear data were alternatively used: the ENEA BUGJEFF311.BOLIB (JEFF-3.1.1) and BUGENDF70.BOLIB (ENDF/B-VII.0) libraries and the ORNL BUGLE-96 (ENDF/B-VI.3) library. Dosimeter cross sections derived from the IAEA IRDF-2002 dosimetry file were employed. The calculated reaction rates for the Rh-103(n,n')Rh-103m, In-115(n,n')In-115m and S-32(n,p)P-32 threshold activation dosimeters and the calculated neutron spectra are compared with the corresponding experimental results
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