Home > Publications database > Severe accident related activities of the research center Jülich/Germany > print |
001 | 888758 | ||
005 | 20240712084607.0 | ||
024 | 7 | _ | |a 10.1016/j.jandt.2020.12.001 |2 doi |
024 | 7 | _ | |a 2128/28155 |2 Handle |
037 | _ | _ | |a FZJ-2020-05187 |
100 | 1 | _ | |a Allelein, Hans-Josef |0 P:(DE-Juel1)130314 |b 0 |u fzj |
245 | _ | _ | |a Severe accident related activities of the research center Jülich/Germany |
260 | _ | _ | |c 2020 |b KeAi Communications Co., Ltd. |
336 | 7 | _ | |a article |2 DRIVER |
336 | 7 | _ | |a Output Types/Journal article |2 DataCite |
336 | 7 | _ | |a Journal Article |b journal |m journal |0 PUB:(DE-HGF)16 |s 1626176131_14726 |2 PUB:(DE-HGF) |
336 | 7 | _ | |a ARTICLE |2 BibTeX |
336 | 7 | _ | |a JOURNAL_ARTICLE |2 ORCID |
336 | 7 | _ | |a Journal Article |0 0 |2 EndNote |
520 | _ | _ | |a In Germany, the Helmholtz Association’s program NUSAFE (Nuclear Waste Management, Safety and Radiation Research) tackles the scientific challenges for the safety of nuclear reactors in the key areas of design basis (DBA) and beyond design basis accidents (BDBA). As one of the three research centers in NUSAFE, the R&D activities at Forschungszentrum Jülich (FZJ) focus on containment phenomena and processes during severe accidents. FZJ supports international efforts to further develop computational methods and tools by providing worldwide unique facilities in the field of wall condensation, aerosol behavior and hydrogen mitigation for advanced code development and validation. Development of computational fluid dynamics (CFD) tools for containment application aims at the integration of existing knowledge and the transfer of research results into application. All research activities are integrated into international collaborations and projects. |
536 | _ | _ | |a 162 - Reactor Safety (POF3-162) |0 G:(DE-HGF)POF3-162 |c POF3-162 |f POF III |x 0 |
588 | _ | _ | |a Dataset connected to CrossRef |
700 | 1 | _ | |a Reinecke, Ernst-Arndt |0 P:(DE-Juel1)130400 |b 1 |e Corresponding author |
700 | 1 | _ | |a Kelm, Stephan |0 P:(DE-Juel1)130361 |b 2 |
700 | 1 | _ | |a Klauck, Michael |0 P:(DE-Juel1)143718 |b 3 |u fzj |
773 | _ | _ | |a 10.1016/j.jandt.2020.12.001 |0 PERI:(DE-600)3072062-X |p 131-143 |t International Journal of Advanced Nuclear Reactor Design and Technology |v 2 |y 2020 |x 2468-6050 |
856 | 4 | _ | |u https://juser.fz-juelich.de/record/888758/files/Allelein.pdf |y OpenAccess |
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910 | 1 | _ | |a Forschungszentrum Jülich |0 I:(DE-588b)5008462-8 |k FZJ |b 0 |6 P:(DE-Juel1)130314 |
910 | 1 | _ | |a Forschungszentrum Jülich |0 I:(DE-588b)5008462-8 |k FZJ |b 1 |6 P:(DE-Juel1)130400 |
910 | 1 | _ | |a Forschungszentrum Jülich |0 I:(DE-588b)5008462-8 |k FZJ |b 2 |6 P:(DE-Juel1)130361 |
910 | 1 | _ | |a Forschungszentrum Jülich |0 I:(DE-588b)5008462-8 |k FZJ |b 3 |6 P:(DE-Juel1)143718 |
913 | 0 | _ | |a DE-HGF |b Energie |l Nukleare Entsorgung und Sicherheit sowie Strahlenforschung |1 G:(DE-HGF)POF3-160 |0 G:(DE-HGF)POF3-162 |3 G:(DE-HGF)POF3 |2 G:(DE-HGF)POF3-100 |4 G:(DE-HGF)POF |v Reactor Safety |x 0 |
914 | 1 | _ | |y 2021 |
915 | _ | _ | |a OpenAccess |0 StatID:(DE-HGF)0510 |2 StatID |
915 | _ | _ | |a Creative Commons Attribution-NonCommercial-NoDerivs CC BY-NC-ND 4.0 |0 LIC:(DE-HGF)CCBYNCND4 |2 HGFVOC |
920 | _ | _ | |l yes |
920 | 1 | _ | |0 I:(DE-Juel1)IEK-6-20101013 |k IEK-6 |l Nukleare Entsorgung und Reaktorsicherheit |x 0 |
980 | 1 | _ | |a FullTexts |
980 | _ | _ | |a journal |
980 | _ | _ | |a VDB |
980 | _ | _ | |a UNRESTRICTED |
980 | _ | _ | |a I:(DE-Juel1)IEK-6-20101013 |
981 | _ | _ | |a I:(DE-Juel1)IFN-2-20101013 |
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