[en] Full text: The possibilities of the TALYS code system were presented. A high degree of automation and reproducibility enables to approach various nuclear data issues in an efficient way. An important one is covariance data, and the two main outlets of the code system for this are the TALYS Evaluated Nuclear Data Library, TENDL, and Total Monte Carlo. TENDL is a complete nuclear reaction database for all projectiles and basically all nuclides in the nuclide chart. A complete representation of covariance data is given in TENDL for MF31-35. The global approach does not allow to perform too detailed studies on a nuclide-by-nuclide level, and general models for uncertainties for TALYS parameters and resonance parameters are used. A similar approach is performed for fission quantities such as the pfns and nu-bar. However, for many nuclides a set of adjusted model parameters + uncertainties + 'non-physical evaluation actions' is stored to be used in future versions of TENDL. Implementation of Unified Monte Carlo is a remaining challenge. Total Monte Carlo means that the random variation of TALYS and resonance parameters, experimental data, ENDF-6 data file creation, processing and applied reactor calculation is seen as a single loop in a Monte Carlo process. This entirely avoids the issue of determining and storing covariance data of cross sections and other quantities in the ENDF-6 format. The only correlations that need to be established are the ones at the beginning of the loop: parameter correlations and correlations of experimental data. Of course, correlations between e.g. k-eff, power rates, and any other quantity will emerge at the end of the process. Full uncertainty propagation examples were given for ICSBEP criticality benchmarks and the sodium cooled fast reactor (SFR), with probability distributions for k-eff, the void coefficient and final inventories. A short demonstration of a third possibility was given: variation of cross sections within their assigned uncertainties allows performing a Monte Carlo search for the best possible library with respect to integral data. The method was presented for Pu-239, and merely demonstrates current computational possibilities; since it is too early to claim that the found 'best' library is indeed better than the existing ones.

[en] The NEA Data Bank operates as an international centre of reference for its member countries with respect to basic nuclear tools, such as computer codes and nuclear data, used for the analysis and prediction of phenomena in the nuclear field. It provides a direct service to its users by acquiring, developing, improving and validating these tools and making them available as requested. In the continuity of WPEC Subgroup 30 work on improving the accessibility and quality of the EXFOR database, the NEA Data Bank initiated a number of activities to further improve and validate its nuclear databases. In particular, it was proposed to perform a comprehensive review of cross-section data in the EXFOR database. This report describes the development of an efficient review system and its application to more than 10,000 cross-section data sets of neutron-induced threshold and activation reactions. The current report is set up as follows. In Section 2 it is outlined how the original EXFOR data collection is transformed into a database that can be subjected to a statistical analysis. In Section 3, a classification for scoring of EXFOR data sets is proposed. Next, in Section 4 the goodness-of-fit estimators that lead to the scoring are defined. Finally a graphical comparison is presented of all experimental data, together with the available major nuclear data libraries, covered in this paper. (author)

[en] Purpose of the meeting: - Objective: • Review existing nuclear data processing tools and code capabilities • Web Interfaces and API Developments • User Feedback and New Demands - Key Discussion Points: • Challenges in data format conversion and data store • Data Pipeline, Data Model, and Data Format • Best Practices for IAEA Nuclear Data Portal • Establishing efficiency and usability of data • Requirements (requests to the IAEA Nuclear Data Portal) - Positive side effects: • Facilitate information exchange • Networking opportunities for developers • Encourage more collaborations, promote inter-operativities

[en] Introduction: • TALYS • Global assessment of experimental data and outlier assignment • Consistent and automated parameter fitting • Special case: Th232(p,x)Ac225 • Conclusions

[en] This presentation aims to open the discussion how scientific nuclear reaction data can be best be brought to the users. As GUI's are no longer the only way to access data, a scheme for basic nuclear data retrieval needs to be set to allow both computational access, though web-api's or similar tools, to the data and plotting abilities. While quite some progress has been made for nuclear structure (ENSDF) data (see other contributions to this meeting), the tools for arguably the most important reaction databases, EXFOR and ENDF, are not yet in a state of general access: the user is forced to understand the ENDF and EXFOR logic and to work through a variety of format and exception rules. Some initiatives are halfway. Modest examples by the author given here are EXFORtables and ENDFtables, to represent experimental and evaluated nuclear reaction data respectively, both meant to represent very format and database specific data into easy accessible form for nuclear scientists Other, more complete, tools by others for this are underway but still need to prove its success and comprehensiveness. A relatively light unifying format called YANDF (Yet Another Nuclear Data Format) is proposed. Several relevant nuclear databases require an update, both in completeness and in format unification. Examples are thermal neutron cross sections, resonance integrals, resonance parameters, Maxwellian-averaged cross sections, average radiative widths, evaluated gamma activation data, etc. etc. If these and the other above mentioned databases should ever make it to ML applications, rich metadata will be required.

[en] A review is given of the topics of ND2001 that deal with nuclear theories, models and evaluations. (author)

[en] Full text: TALYS is a software package for the simulation of nuclear reactions below 200 MeV. It is used world-wide for the analysis and prediction of nuclear reactions and is based on state-of-art nuclear structure and nuclear reaction models. We will present the overall status of the code, in particular the recent TALYS-2.0 release. Next, a global validation of the latest photon strength functions and level density models using relevant experimental databases will be given. Finally, we will share some possible TALYS development plans for the next decade.

[en] A new web tool has been developed which allows to directly predict the production yield of a medical isotope on the basis of user input. The first version is restricted to isotopes produced by charged-particle accelerators. The user can specify the characteristics of the accelerator, such as the projectile (proton, deuteron, triton, Helium-3 or alpha particle), current in mA, the incident and exit energy, and specify the target material and the desired produced radioisotope. After a simple mouse click the required isotopic yield as a function of irradiation and cooling time, as well as a complete description of all the produced impurities is obtained, virtually instantaneous. The medical isotope browser is based on 4 essential ingredients, which will be discussed in some detail: • A web-based Graphical User Interface • An efficient solution of the production and depletion equations • A radioactive decay data library • A complete cross section library A live demonstration of the Medical Isotope Browser will be given for some important examples as Tc-99m, Ac-225 and Ga-68. (author)

[en] Nuclear Data Section Outlook for 2024-2025: • Technical Meeting on (alpha,n) reactions for spent fuel and criticality safety • New CRP on nuclear level densities, for better nuclear reaction simulations (model codes) • Further modernization on web interfaces for nuclear data retrieval, using a combination of Python and JSON tools • Large (60-100 participants) Technical Meeting on Compound Nuclear Reactions and Related Areas • Finalization and continuation of CRPs on atomic and molecular data for nuclear fusion • Joint ICTP-IAEA workshop on Monte Carlo Radiation Transport Codes and Associated Data Needs for Medical Applications • Finalize CRP on fission product yield nuclear data

[en] New ENDF-6 formatted nuclear data libraries are presented for ^{40,42,43,44,46,48}Ca and ⁴⁵Sc, for incident neutrons and protons. Apart from the resonance range, which we have adopted from the best available source in existing libraries, the nuclear data evaluations are completely revised in the 0-20MeV energy range, and, moreover, extend up to 200 MeV. This collection of isotopic evaluations is created by using the nuclear model code TALYS with a consistent set of input parameters for all isotopes. The most important nuclear reaction models needed for our data files are described. We have intended to make these evaluations complete in their description of reaction channels and use a consistent method to store the data in ENDF-6 format, which include cross sections, angular distributions, double-differential spectra, discrete and continuum photon production cross sections, and residual production (activation) cross sections including isomers. It is shown that the data present in our libraries give an improved agreement with the existing basic experimental data. (author)