FISPACT-II: An Advanced Simulation System for Activation, Transmutation and Material Modelling

Sublet, J.‐Ch.; Eastwood, J.W.; Morgan, J.G.; Gilbert, Mark R.; Fleming, Michael; Arter, W.

doi:10.1016/j.nds.2017.01.002

Cited by 157 publications

(77 citation statements)

References 28 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…In the ANITA-IEAF code new MT numbers have been introduced, from 151 to 200, the same as in FISPACT code [12], that allow describing reactions with up to 8 emitted particles corresponding to a set of unallocated numbers in the standard ENDF-6 format.…”

Section: Main Features Of the Updated Anita-ieaf Activation Code Packagementioning

confidence: 99%

“…In the present calculations the latest TENDL-2014 [18] evaluated cross section data library, in the 709-energy group structure contained in the package released by OECD-NEADB [19], was used. These data are provided in ENDF-6 format.…”

Section: Activation Cross Section Libraries Comparisonmentioning

confidence: 99%

“…The ANITA-IEAF results are also compared with those obtained through the FISPACT-II code [12], contained in the European Activation System-II (EASY-II) [13], using the same EAF-2010 neutron activation cross section library, in order to evaluate the responses of the two codes.…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

ANITA-IEAF activation code package – updating of the decay and cross section data libraries and validation on the experimental data from the Karlsruhe Isochronous Cyclotron

Frisoni

2017

EPJ Web Conf.

View full text Add to dashboard Cite

Abstract. ANITA-IEAF is an activation package (code and libraries) developed in the past in ENEABologna in order to assess the activation of materials exposed to neutrons with energies greater than 20MeV. An updated version of the ANITA-IEAF activation code package has been developed. 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 the DEMO Oriented Neutron Source (DONES), in which a considerable amount of neutrons with energies above 20 MeV is produced. The present paper summarizes the main characteristics of the updated version of ANITA-IEAF, able to use decay and cross section data based on more recent evaluated nuclear data libraries, i.e. the JEFF-3.1.1 Radioactive Decay Data Library and the EAF-2010 neutron activation cross section library. In this paper the validation effort related to the comparison between the code predictions and the activity measurements obtained from the Karlsruhe Isochronous Cyclotron is presented. In this integral experiment samples of two different steels, SS-316 and F82H, pure vanadium and a vanadium alloy, structural materials of interest in fusion technology, were activated in a neutron spectrum similar to the IFMIF neutron field.

show abstract

Section: Main Features Of the Updated Anita-ieaf Activation Code Packagementioning

confidence: 99%

Section: Activation Cross Section Libraries Comparisonmentioning

confidence: 99%

See 1 more Smart Citation

ANITA-IEAF activation code package – updating of the decay and cross section data libraries and validation on the experimental data from the Karlsruhe Isochronous Cyclotron

Frisoni

2017

EPJ Web Conf.

View full text Add to dashboard Cite

show abstract

“…The preparation of nuclear data from diverse sources for use in FISPACT-II [1] was streamlined and simplified by following as closely as possible the forms of data format described in the ENDF-6 format manual [2].…”

Section: Multigroup Constantsmentioning

confidence: 99%

From cutting-edge pointwise cross-section to groupwise reaction rate: A primer

2017

View full text Add to dashboard Cite

Abstract. The nuclear research and development community has a history of using both integral and differential experiments to support accurate lattice-reactor, nuclear reactor criticality and shielding simulations, as well as verification and validation efforts of cross sections and emitted particle spectra. An important aspect to this type of analysis is the proper consideration of the contribution of the neutron spectrum in its entirety, with correct propagation of uncertainties and standard deviations derived from Monte Carlo simulations, to the local and total uncertainty in the simulated reactions rates (RRs), which usually only apply to one application at a time. This paper identifies deficiencies in the traditional treatment, and discusses correct handling of the RR uncertainty quantification and propagation, including details of the cross section components in the RR uncertainty estimates, which are verified for relevant applications. The methodology that rigorously captures the spectral shift and cross section contributions to the uncertainty in the RR are discussed with quantified examples that demonstrate the importance of the proper treatment of the spectrum profile and cross section contributions to the uncertainty in the RR and subsequent response functions.The recently developed inventory code FISPACT-II, when connected to the processed nuclear data libraries TENDL-2015, ENDF/B-VII.1, JENDL-4.0u or JEFF-3.2, forms an enhanced multi-physics platform providing a wide variety of advanced simulation methods for modelling activation, transmutation, burnup protocols and simulating radiation damage sources terms. The system has extended cutting-edge nuclear data forms, uncertainty quantification and propagation methods, which have been the subject of recent integral and differential, fission, fusion and accelerators validation efforts. The simulation system is used to accurately and predictively probe, understand and underpin a modern and sustainable understanding of the nuclear physics that is so important for many areas of science and technology; advanced fission and fuel systems, magnetic and inertial confinement fusion, high energy, accelerator physics, medical application, isotope production, earth exploration, astrophysics and homeland security.

show abstract

“…In order to meet the simulation demands for emerging and next-generation technologies, new technologies are required to extend our capabilities and anticipate challenges -including those of nuclear data and activation-inventory simulation. Over the past decade, the UKAEA has focused on the extension of its main nuclear observables code, FISPACT-II [1], developing it to best employ the rapidly maturing TALYS-generated Evaluated Nuclear Data Libraries (TENDL) for neutron and charged particle irradiation [2]. This has culminated in several verification and validation exercises for both FISPACT-II and its associated nuclear data libraries, covering a range of approaches summarised in this paper.…”

Section: Introductionmentioning

confidence: 99%

TALYS/TENDL verification and validation processes: Outcomes and recommendations

et al. 2017

View full text Add to dashboard Cite

Abstract. The TALYS-generated Evaluated Nuclear Data Libraries (TENDL) provide truly general-purpose nuclear data files assembled from the outputs of the T6 nuclear model codes system for direct use in both basic physics and engineering applications. The most recent TENDL-2015 version is based on both default and adjusted parameters of the most recent TALYS, TAFIS, TANES, TARES, TEFAL, TASMAN codes wrapped into a Total Monte Carlo loop for uncertainty quantification. TENDL-2015 contains complete neutron-incident evaluations for all target nuclides with Z ≤116 with half-life longer than 1 second (2809 isotopes with 544 isomeric states), up to 200 MeV, with covariances and all reaction daughter products including isomers of halflife greater than 100 milliseconds. With the added High Fidelity Resonance (HFR) approach, all resonances are unique, following statistical rules. The validation of the TENDL-2014/2015 libraries against standard, evaluated, microscopic and integral cross sections has been performed against a newly compiled UKAEA database of thermal, resonance integral, Maxwellian averages, 14 MeV and various accelerator-driven neutron source spectra. This has been assembled using the most up-to-date, internationally-recognised data sources including the Atlas of Resonances, CRC, evaluated EXFOR, activation databases, fusion, fission and MACS. Excellent agreement was found with a small set of errors within the reference databases and TENDL-2014 predictions.

show abstract

FISPACT-II: An Advanced Simulation System for Activation, Transmutation and Material Modelling

Cited by 157 publications

References 28 publications

ANITA-IEAF activation code package – updating of the decay and cross section data libraries and validation on the experimental data from the Karlsruhe Isochronous Cyclotron

ANITA-IEAF activation code package – updating of the decay and cross section data libraries and validation on the experimental data from the Karlsruhe Isochronous Cyclotron

From cutting-edge pointwise cross-section to groupwise reaction rate: A primer

TALYS/TENDL verification and validation processes: Outcomes and recommendations

Contact Info

Product

Resources

About