[en] The Hauser-Feshbach formalism and Hill-Wheeler formula provide a reliable framework for describing fission cross-sections, particularly for fast neutrons, integrated into various nuclear reaction model codes such as TALYS, EMPIRE, CCONE and CoH. However, predicting fission cross-sections using this method relies on parameters like barrier heights, necessitating adjustments to closely match experimental data. The EXFOR library has a large number of experimental datasets, and it enables us to perform evaluation by least-squares analysis of the EXFOR datasets without a physics model. The least-squares analysis code SOK developed for simultaneous evaluation for the JENDL project has been successfully applied to evaluation of the 233,235,238U and 239,240,241Pu fission cross sections for fast neutrons. As nuclear data libraries evolve, Nuclear Reaction Data Centres (NRDCs) increasingly prioritize compiling experimental uncertainty and covariance information. To facilitate this, the EXFOR format has expanded to include correlation property flags and adopt computer-readable matrix formats, enhancing data accessibility and usability. Moreover, there is growing interest in acquiring new experimental datasets relevant to simultaneous evaluations, notably from time-of-flight facilities such as CERN n_TOF and LANSCE. In response to these advancements, we embarked on recreating the simultaneous evaluation of the neutron-induced fission cross section of 232Th and 237Np in the fast neutron region. These nuclides were chosen since (1) 232Th energy dependent cross section and fission neutron spectrum averaged cross section show inconsistency, and (2) 237Np is sometimes used as a reference and better to be a part of our simultaneous evaluation framework. The experimental 232Th and 237Np fission cross sections and their ratios to fission cross sections of other nuclides such as 235,238U in the EXFOR library were reviewed and analyzed. Experimental covariances were estimated for each experimental dataset and incorporated in the new evaluation. The newly evaluated cross sections were validated against spectrum-averaged cross sections measured in the 252Cf spontaneous fission neutron standard field.

[en] The neutron scattering cross sections compiled with EL in REACTION SF3 in EXFOR entries often include contribution of inelastic scattering to low-lying excitation levels due to insufficient energy resolution. It disturbs people who performs evaluation with models, and it has been urged to improve the situation. Therefore, we performed review of the relevant EXFOR entries by the following tasks: 1. extracting EXFOR entries compiling neutron elastic scattering angular differential and integrated cross sections which (1) incident energy is higher than 1.5 MeV, (2) excitation energy of the 1st level less than 200 keV, and (3) target mass heavier than 40 (Ca); 2. checking their source articles to find if there is any description on inclusion of the inelastic scattering contribution; 3. summarize the suggestions for update of each EXFOR entry.

[en] The world-wide network of nuclear reaction data centers (NRDC) has, for about 40 years, provided data services to the scientific community. This network covers all types of nuclear reaction data, including neutron-induced, charged-particle-induced, and photonuclear data, used in a wide range of applications, such as fission reactors, accelerator driven systems, fusion facilities, nuclear medicine, materials analysis, environmental monitoring, and basic research. The now 13 nuclear data centers included in the NRDC are dividing the efforts of compilation and distribution for particular types of reactions and/or geographic regions all over the world. A central activity of the network is the collection and compilation of experimental nuclear reaction data and the related bibliographic information in the EXFOR and CINDA databases. Many of the individual data centers also distribute other types of nuclear data information, including evaluated data libraries, nuclear structure and decay data, and nuclear data reports. The network today ensures the world-wide transfer of information and coordinated evolution of an important source of nuclear data for current and future nuclear applications

[en] The International Network of Nuclear Reaction Data Centres (NRDC) consists of 14 data centers from 10 countries and 2 international organizations, and is collaborating for compilation, exchange and dissemination of various types of nuclear reaction data information. The nuclear data centers common data collection, the EXFOR library today contains experimental information and numerical data from more than 18,000 experiments consisting of more than 134,000 data sets mainly of nuclear reaction data for incident neutrons, charged-particles and photons with incident energy lower than 1 GeV. A brief history and the current status of NRDC collaboration are presented for EXFOR as well as CINDA and ENDF.

[en] Digitization is not avoidable for compilation of both old and new articles. In addition to accurate digitization of values and uncertainties from the data points and error bars, the compiler should process the outputs from the digitization software appropriately when the outputs are included in EXFOR entries. Usually experimentalists report values and uncertainties by the same number of digits (e.g., 1.00 ± 0.03 barn, 1.000 ± 0.031 barn). The notation of uncertainties by parenthesized values (e.g., 1.00(3) barn) supports this rule, and EXFOR compilers are also expected to follow the same convention. Note that the usage of the parenthesized uncertainty expression may depend on authors (e.g., 1.00(3.1) or 1.00(31) for 1.00 ± 0.031 barn) and the authors are expected to describe its usage explicitly in their articles. This paper discusses rounding of digitized values and evaluation of digitization accuracy

[en] Accurate neutron-induced activation cross-section data are of interest in many fields of science and applications. Such data are needed for calculations and analysis of neutron transport, activation of materials, gas production and radiation damage, dose rates etc. Experimental data provide bases for the parameterization of reaction cross section calculations, and for the assessment of nuclear models and evaluated data libraries. Activation technique in combination with gamma spectrometry is well known and widely used method for neutron-induced reaction cross-section measurements. However, in some cases considerable differences exist between the results from different experiments. A careful consideration of the all factors that may affect each particular measurement is needed in order to obtain reliable data. Measured data are of little value until they are made conveniently available for users and evaluators. The International Network of Nuclear Reaction Data Centres (NRDC) collaborates in collection, compilation and dissemination of experimental nuclear reaction data in the EXFOR data library. In the present work some aspects of the "5"8Ni(n,p)"5"8Co activation cross-section measurements at two different experimental facilities and EXFOR compilation files will be presented

[en] This is the second year as the Kazakhstan team is actively engaged in the compilation of articles to EXFOR database. Since our report in the 5^th AASPP workshop (Mumbai, September 2014, six articles have been compiled. All articles report charged-particle induced reaction experimental works performed by using the U-150M cyclotron in Almaty or the DC-60 cyclotron in Astana.

[en] Cross section and other experimental neutron-induced reaction data measured under broad neutron spectra have been compiled in the EXFOR Library maintained by the International Network of Nuclear Reaction Data Centres (NRDC). In the current EXFOR Formats rule, the neutron field used in the measurement is indicated by a 'modifier' as a part of the code under the keyword REACTION, and its characteristic energy is coded with the measured cross section. Following the introduction of Westcott's convention, two spectrum modifiers MXW and SPA and two definitions of Maxwellian averaged cross sections (MACS) are presently used in compilation practice. To remove ambiguity, the compilation rules for neutron spectrum averaged quantity and representative energy are discussed in this Appendix.

[en] The International Network of Nuclear Reaction Data Centres (NRDC) provides nuclear reaction data services to users through collection and compilation of experimental nuclear reaction data in the EXFOR database. The database includes neutron-induced, charged-particle-induced, and photonuclear data for projectile energies up to 1 GeV. Sophisticated search options and user-friendly retrieval interface for downloading data in different formats have been developed at IAEA Nuclear Data Section. Additional output options such as data plotting capabilities are provided as well. The database is constantly revised and extended and at present contains about 20,000 experimental works accumulated in its 40 years of history. The paper will present several recent IAEA Nuclear Data Section activities related to the development of the EXFOR database and retrieval system. (authors)

[en] Full text: The EXFOR database is a global repository of experimental nuclear reaction data and associated information developed and maintained by the international collaboration of Nuclear Reaction Data Centres (NRDC) under the auspices of the International Atomic Energy Agency Nuclear Data Section for data exchange since 1970. The high degree of coverage of all published experimental studies within the scope of EXFOR and the high quality of the compilations made the EXFOR library a valuable source for information and analysis. The open literature (journals, conference proceedings, report etc.) is regularly scanned to identify publications reporting nuclear reaction data. In addition the EXFOR completeness is periodically checked and missing publications are compiled. The compilation of the articles in a timely manner and the efforts to minimise the time from the publication to the uploading of the EXFOR entry in database is important to provide up-to-date information to users. Nuclear Data Section has recently organised Consultants’ Meetings (CM) in order to improve the EXFOR compilation for specific type of data and provide the necessary information for the proper analysis of the experimental data. Guidelines for compilation of the time-of-flight measurements and the thermal neutron scattering experiments were prepared and supplementary data (spectrometers’ response function, phonon spectrum, structural parameters etc.) will be provided to users. The status of the EXFOR compilation statistics and some new developments in the compilation of the experimental nuclear reaction data will be presented. (author)