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1Report
المؤلفون: Kliem, S., Nikitin, E., Rachamin, R., Glivici-Cotruta, V.
مصطلحات موضوعية: DYN3D, SERPENT, Natrium gekühlter Reaktor, thermomechanische Modelle, Validierung, DYN3D, SERPENT, sodium cooled reactor, thermomechanical models, validation
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2Report
المؤلفون: Kliem, S., Nikitin, E., Rachamin, R., Glivici-Cotruta, V.
Thesis Advisors: Helmholtz-Zentrum Dresden - Rossendorf
مصطلحات موضوعية: DYN3D, SERPENT, Natrium gekühlter Reaktor, thermomechanische Modelle, Validierung, sodium cooled reactor, thermomechanical models, validation
وصف الملف: application/pdf
Relation: dcterms:isPartOf:Wissenschaftlich-Technische Berichte; HZDR-086
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3Report
المؤلفون: Jobst, M., Kliem, S., Kozmenkov, Y., Wilhelm, P.
مصطلحات موضوعية: Druckwasserreaktor, Schwere Störfälle, Notfallmaßnahmen, ATHLET-CD-Simulation, Pressurized Water Reactor, Severe accidents, Accident management measures, ATHLET-CD simulations
Relation: urn:nbn:de:bsz:d120-qucosa-237182; qucosa:22349
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4Report
المؤلفون: Kliem, S., Grundmann, U., Rohde, U.
المصدر: Wissenschaftlich-Technische Berichte / Forschungszentrum Rossendorf; FZR-357 Oktober 2002
مصطلحات موضوعية: transient analysis, accident scenarios, pressurised water reactors, neutron kinetics, thermal hydraulics, overcooling transients, steam line break, code validation, benchmark problems
Relation: urn:nbn:de:bsz:d120-qucosa-237209; qucosa:22351
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5Report
المؤلفون: Grunwald, G., Kliem, S., Höhne, T., Rohde, U., Prasser, H.-M., Richter, K.-H., Weiß, F.-P.
المصدر: Wissenschaftlich-Technische Berichte / Forschungszentrum Rossendorf; FZR-348 Juli 2002
مصطلحات موضوعية: pressurised water reactors, pressure vessel, coolant flow, turbulent mixing, test facility, stationary flow, forced flow, natural circulation, conductivity measurement, wire-mesh sensor
Relation: urn:nbn:de:bsz:d120-qucosa-237209; qucosa:22351
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6Report
المؤلفون: Mittag, S., et, al, Grundmann, U., Kliem, S., Rindelhardt, U., Kozmenkov, Y.
المصدر: Wissenschaftlich-Technische Berichte / Forschungszentrum Rossendorf; FZR-408
Relation: urn:nbn:de:bsz:d120-qucosa-237209; qucosa:22351
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7Report
المؤلفون: Farkas, I., Aszodi, A., Elter, J., Klepac, J., Remis, J., Kliem, S., Höhne, T., Toppila, T., Boros, I.
المصدر: Wissenschaftlich-Technische Berichte / Forschungszentrum Rossendorf; FZR-431 2005
مصطلحات موضوعية: fluid mixing, flow distribution, velocity filed, nuclear power plant, commissioning experiments, experimental data base, computational fluid dynamics
Relation: urn:nbn:de:bsz:d120-qucosa-237209; qucosa:22351
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8Report
المؤلفون: Hemström, B., Mühlbauer, P., Lycklama a. Nijeholt, J.-A., Farkas, I., Boros, I., Aszodi, A., Scheuerer, M., Dury, T., Rohde, U., Höhne, T., Kliem, S., Vyskocil, L., Toppila, T., Klepac, J., Remis, J.
المصدر: Wissenschaftlich-Technische Berichte / Forschungszentrum Rossendorf; FZR-432 2005
مصطلحات موضوعية: turbulent mixing, flow distribution, nuclear reactors, experimental data base, computational fluid dynamics, best practice guidelines
Relation: urn:nbn:de:bsz:d120-qucosa-237209; qucosa:22351
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9Report
المؤلفون: Rohde, U., Grundmann, U., Kliem, S.
المصدر: Wissenschaftlich-Technische Berichte / Forschungszentrum Rossendorf; FZR-438 2005
مصطلحات موضوعية: pressurized water reactor, accident analysis, coupled neutronics-thermohydraulic codes, boron dilution, main steam line break, coolant mixing
Relation: urn:nbn:de:bsz:d120-qucosa-237209; qucosa:22351
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10Academic Journal
المؤلفون: Sanchez-Espinoza, V. H., Valtavirta, V., Bencik, M., Kliem, S., Queral, C., Chochet, S., Smith, P., Uffelen, P. van, Seidl, M., Schneidesch, C., Grishchenko, D., Lestani, H.
مصطلحات موضوعية: ddc:600, Technology, info:eu-repo/classification/ddc/600
وصف الملف: application/pdf
Relation: https://publikationen.bibliothek.kit.edu/1000161463; https://publikationen.bibliothek.kit.edu/1000161463/151176357; https://doi.org/10.5445/IR/1000161463
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11Academic Journal
المؤلفون: Sanchez-Espinoza, V. H., Gabriel, S., Suikkanen, H., Valtavirta, V., Bencik, M., Kliem, S., Queral, C., Farda, A., Smith, P., Uffelen, P. van, Seidl, M., Schneidesch, C., Grishchenko, D., Lestani, H.
مصطلحات موضوعية: ddc:600, Technology, info:eu-repo/classification/ddc/600
وصف الملف: application/pdf
Relation: https://publikationen.bibliothek.kit.edu/1000158146; https://publikationen.bibliothek.kit.edu/1000158146/150624547; https://doi.org/10.5445/IR/1000158146
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12
المؤلفون: Viebach, M., Lange, C., Kliem, S., Demaziere, Christophe, 1973, Rohde, U., Hennig, D., Hurtado, A.
المصدر: Annals of Nuclear Energy. 166
مصطلحات موضوعية: Deterministic reactor modelling, CORE SIM, DYN3D, Neutron noise
وصف الملف: electronic
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13Academic Journal
المؤلفون: Sanchez-Espinoza, Victor Hugo, Suikkanen, H., Valtavirta, V., Bencik, M., Kliem, S., Queral, C., Farda, A., Smith, P., Van Uffelen, P., Seidl, M., Schneidesch, C., Grishchenko, D., Lestani, H.
مصطلحات موضوعية: ddc:600, Technology, info:eu-repo/classification/ddc/600
وصف الملف: application/pdf
Relation: https://publikationen.bibliothek.kit.edu/1000147917; https://publikationen.bibliothek.kit.edu/1000147917/148919410; https://doi.org/10.5445/IR/1000147917
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14Conference
المؤلفون: Sanchez-Espinoza, V.H., Gabriel, S., Suikkanen, H., Valtavirta, V., Bencik, M., Kliem, S., Queral, C., Cochet, S., Smith, P., Van Uffelen, P., Seidl, M., Schneidesch, Ch., Grishchenko, D., Lestani, H.
المصدر: M&C 2023, The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Niagara Falls, Ontario, Canada, 13-17 August, 2023
Relation: https://doi.org/10.5281/zenodo.10810384; https://doi.org/10.5281/zenodo.10810385; oai:zenodo.org:10810385
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15Electronic Resource
المؤلفون: (0000-0001-5362-1925) Diaz Pescador, E., (0000-0002-7810-1245) Bilodid, Y., (0000-0002-0151-3137) Jobst, M., (0000-0001-6654-6434) Kliem, S.
المصدر: Nuclear Engineering and Design 418(2024), 112909
مصطلحات الفهرس: NuScale-SMR, iPWR, Boron dilution, Steam line break, Serpent-DYN3D-ATHLET, info:eu-repo/semantics/publishedVersion, doc-type:article, Text
URL:
https://www.hzdr.de/publications/Publ-38564-1
info:eu-repo/semantics/reference/doi/10.1016/j.nucengdes.2024.112909
info:eu-repo/semantics/altIdentifier/purl/https://www.hzdr.de/publications/Publ-38564-1 -
16Electronic Resource
المصدر: Nuclear Engineering and Design 421(2024), 113059
مصطلحات الفهرس: Condensation heat transfer, passive safety systems, system code development, ATHLET, AC2, info:eu-repo/semantics/publishedVersion, doc-type:article, Text
URL:
https://www.hzdr.de/publications/Publ-37143-1
info:eu-repo/semantics/reference/doi/10.1016/j.nucengdes.2024.113059
info:eu-repo/semantics/altIdentifier/purl/https://www.hzdr.de/publications/Publ-37143-1 -
17Electronic Resource
المؤلفون: Grahn, A., (0000-0001-5362-1925) Diaz Pescador, E., (0000-0002-7810-1245) Bilodid, Y., (0000-0001-6654-6434) Kliem, S.
المصدر: Workshop on Core and Plant Simulation with an Emphasis on Fuel Behaviour in Light Water Reactor based Small Modular Reactors, 27.-29.02.2024, Wien, Österreich
مصطلحات الفهرس: small modular reactors, steam line break, thermal-hydraulics, reactor dynamics, system codes, computational fluid dynamics, info:eu-repo/semantics/publishedVersion, doc-type:lecture, Text
URL:
https://www.hzdr.de/publications/Publ-38855-1
info:eu-repo/semantics/altIdentifier/purl/https://www.hzdr.de/publications/Publ-38855-1 -
18Academic Journal
المؤلفون: Hilbert, A., Witte, A., Meule, A., Braehler, E., Kliem, S.
المصدر: Nutrients
وصف الملف: application/pdf
Relation: info:eu-repo/semantics/altIdentifier/pmid/35565829; http://hdl.handle.net/21.11116/0000-000A-7E6F-E; http://hdl.handle.net/21.11116/0000-000A-7E71-A
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19Academic Journal
المؤلفون: Diaz-Pescador, E., Schäfer, F., Kliem, S.
المساهمون: Bundesministerium für Wirtschaft und Energie
المصدر: Nuclear Engineering and Technology ; volume 54, issue 9, page 3567-3579 ; ISSN 1738-5733
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20Conference
المؤلفون: Morelova I., Heidet F., Di Piazza I., Yang X., Gerschenfeld A., Kumaresan N., Jeong J. -H., Volkov A., Vaghetto R., Kriventsev V., Wootan D. W., Hassan H., Wang J., Kliem S., Giannetti F., Hong J., Wallenius J., Omotowa O., Sumner T., Casella A. M., Lorusso P., Lu D., Fridman E., Petruzzi A., Stempniewicz M., Fiorina C., Kelly J., Moisseytsev A., Nelson J. V., Martelli D., Zhang D., Rineiski A., Tanaka M., Tsaun S., Mikityuk K., Lane J.
المساهمون: Morelova, I., Heidet, F., Di Piazza, I., Yang, X., Gerschenfeld, A., Kumaresan, N., Jeong, J. -H., Volkov, A., Vaghetto, R., Kriventsev, V., Wootan, D. W., Hassan, H., Wang, J., Kliem, S., Giannetti, F., Hong, J., Wallenius, J., Omotowa, O., Sumner, T., Casella, A. M., Lorusso, P., Lu, D., Fridman, E., Petruzzi, A., Stempniewicz, M., Fiorina, C., Kelly, J., Moisseytsev, A., Nelson, J. V., Martelli, D., Zhang, D., Rineiski, A., Tanaka, M., Tsaun, S., Mikityuk, K., Lane, J.
مصطلحات موضوعية: fast reactor, IAEA, LFR, modelling and simulation coordinated research project, SFR, thermal hydraulics
Relation: ispartofbook:International Conference on Nuclear Engineering, Proceedings, ICONE; 30th International Conference on Nuclear Engineering, ICONE 2023; firstpage:1; lastpage:7; numberofpages:7; https://hdl.handle.net/11573/1697653; info:eu-repo/semantics/altIdentifier/scopus/2-s2.0-85178505274
الاتاحة: https://hdl.handle.net/11573/1697653