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FENDL: A library for fusion research and applications

Title: FENDL: A library for fusion research and applications
Authors: Schnabel G.; Aldama D. L.; Bohm T.; Fischer U.; Kunieda S.; Trkov A.; Konno C.; Capote R.; Koning A. J.; Breidokaite S.; Eade T.; Fabbri M.; Flammini D.; Isolan L.; Kodeli I.; Kostal M.; Kwon S.; Laghi D.; Leichtle D.; Nakayama S.; Ohta M.; Packer L. W.; Qiu Y.; Sato S.; Sawan M.; Schulc M.; Stankunas G.; Sumini M.; Valentine A.; Villari R.; Zohar A.
Contributors: Schnabel, G.; Aldama, D. L.; Bohm, T.; Fischer, U.; Kunieda, S.; Trkov, A.; Konno, C.; Capote, R.; Koning, A. J.; Breidokaite, S.; Eade, T.; Fabbri, M.; Flammini, D.; Isolan, L.; Kodeli, I.; Kostal, M.; Kwon, S.; Laghi, D.; Leichtle, D.; Nakayama, S.; Ohta, M.; Packer, L. W.; Qiu, Y.; Sato, S.; Sawan, M.; Schulc, M.; Stankunas, G.; Sumini, M.; Valentine, A.; Villari, R.; Zohar, A.
Publication Year: 2024
Collection: IRIS Università degli Studi di Bologna (CRIS - Current Research Information System)
Subject Terms: FENDL; Nuclear Data Library; Fusion; Verification & Validation
Description: The Fusion Evaluated Nuclear Data Library (FENDL) is a comprehensive and validated collection of nuclear cross section data coordinated by the International Atomic Energy Agency (IAEA) Nuclear Data Section (NDS). FENDL assembles the best nuclear data for fusion applications selected from available nuclear data libraries and has been under development for decades. FENDL contains sub- libraries for incident neutron, proton, and deuteron cross sections including general purpose and activation files used for particle transport and nuclide inventory calculations. In this work, we describe the history, selection of evaluations for the various sub-libraries (neutron, proton, deuteron) with the focus on transport and reactor dosimetry applications, the processing of the nuclear data for application codes (e.g. MCNP), and the development of the TENDL-2017 library which is the currently recommended activation library for FENDL. We briefly describe the IAEA IRDFF library as the recommended library for dosimetry fusion applications. We also present work on validation of the neutron sub-library using a variety of fusion relevant computational and experimental benchmarks using the MCNP transport code and ACE-formatted cross section libraries. A variety of cross section libraries are used for the validation work including FENDL-2.1, FENDL-3.1d, FENDL-3.2, ENDF/B-VIII.0, and JEFF-3.2 with the emphasis on the FENDL libraries. The results of the validation using computational benchmarks showed generally good agreement among the tested neutron cross section libraries for neutron flux, nuclear heating, and primary displacement damage (dpa). Gas production (H/He) in structural materials showed substantial differences to the reference FENDL-2.1 library. The results of the experimental validation showed that the performance of FENDL-3.2b is at least as good and in most cases better than FENDL-2.1. Future work will consider improved evaluations developed by the International Nuclear Data Evaluation Network (INDEN) for materials such as ...
Document Type: article in journal/newspaper
File Description: STAMPA
Language: English
Relation: info:eu-repo/semantics/altIdentifier/wos/WOS:001182104000001; volume:193; firstpage:1; lastpage:78; numberofpages:78; journal:NUCLEAR DATA SHEETS; https://hdl.handle.net/11585/958775; https://www.sciencedirect.com/science/article/pii/S0090375224000012?via=ihub
DOI: 10.1016/j.nds.2024.01.001
Availability: https://hdl.handle.net/11585/958775; https://doi.org/10.1016/j.nds.2024.01.001; https://www.sciencedirect.com/science/article/pii/S0090375224000012?via=ihub
Rights: info:eu-repo/semantics/openAccess ; license:Licenza per Accesso Aperto. Creative Commons Attribuzione - Non commerciale - Non opere derivate (CCBYNCND) ; license uri:iris.PUB17
Accession Number: edsbas.AD382E36
Database: BASE