Search Results - "Stuckert, J."

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  1. 1

    Results of the QUENCH-LOCA experimental program at KIT by Stuckert, J., Grosse, M., Steinbrueck, M., Walter, M., Wensauer, A.

    Published in Journal of nuclear materials (01-06-2020)
    “…The QUENCH-LOCA bundle test series was launched to investigate the influence of the secondary hydriding phenomena on the applicability of the cladding…”
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    Journal Article
  2. 2

    Synopsis and outcome of the QUENCH experimental program by Steinbrück, M., Große, M., Sepold, L., Stuckert, J.

    Published in Nuclear engineering and design (01-07-2010)
    “…The paper gives an overview of the main outcome of the QUENCH program launched in 1997 at the Karlsruhe Institute of Technology (KIT), formerly Karlsruhe…”
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    Journal Article
  3. 3

    Experimental results of the QUENCH-16 bundle test on air ingress by Stuckert, J., Steinbrück, M.

    Published in Progress in nuclear energy (New series) (01-03-2014)
    “…The out-of-pile bundle experiment QUENCH-16 on air ingress was conducted in the electrically heated 21-rod QUENCH facility at KIT in July 2011. It was…”
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    Journal Article
  4. 4

    Hafnium oxidation at high temperature in steam by Guilbert-Banti, S., Viretto, A., Barrachin, M., Tanguy, C., Steinbrück, M., Stuckert, J.

    Published in Journal of nuclear materials (01-07-2021)
    “…To assess the potential impact of using hafnium as absorber material in LWRs in high temperature accidental situations, the oxidation behavior of hafnium was…”
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    Journal Article
  5. 5

    Management of nutritional iron deficiency anemia for young children in the emergency department by McEvoy, Matthew T., Stuckert, Austin J., Castellanos, Maria I., Gilbert, Megan M., Pfeiffer, Thomas, Prudowsky, Zachary, Rios, Xavier, Airewele, Gladstone, Okcu, M. Fatih, Powers, Jacquelyn M.

    Published in Pediatric blood & cancer (01-03-2023)
    “…Background Guidelines for young children with nutritional iron deficiency anemia (IDA) presenting to the emergency department (ED) are lacking, leading to…”
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  6. 6

    Post-test calculation of the QUENCH-17 bundle experiment with debris formation and bottom water reflood using thermal hydraulic and severe fuel damage code SOCRAT/V3 by Vasiliev, A., Stuckert, J.

    Published in Nuclear engineering and design (01-03-2015)
    “…•Modeling of processes in porous debris regions.•Analysis of coolability of massive debris bed.•Complexity of simulation of flow regime near boiling curve. The…”
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  7. 7

    Cladding oxidation during air ingress. Part I: Experiments on air ingress by Stuckert, J., Hózer, Z., Kiselev, A., Steinbrück, M.

    Published in Annals of nuclear energy (01-07-2016)
    “…•Summary of recent experiments on air ingress.•Reaction of nitrogen with α-Zr(O) under oxygen starvation conditions.•Formation of very porous and fragile…”
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  8. 8

    A comparison of core degradation phenomena in the CORA, QUENCH, Phébus SFD and Phébus FP experiments by Haste, T., Steinbrück, M., Barrachin, M., de Luze, O., Grosse, M., Stuckert, J.

    Published in Nuclear engineering and design (01-03-2015)
    “…•The results of the experiments CORA, QUENCH and Phébus SFD/FP are summarised.•All phenomena expected up to melt movement to the lower head are shown…”
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  9. 9

    Post-test analyses of the CORA-15 bundle test with the system codes ATHLET-CD and SOCRAT by Stuckert, J., Austregesilo, H., Bals, Ch, Hollands, Th, Kiselev, A., Tomashchik, D., Yudina, T.

    Published in Nuclear engineering and design (01-02-2019)
    “…•A high temperature bundle test was performed with rods pressurized to 6 MPa.•Results of post-test modelling performed by the ATHLET-CD and SOCRAT codes were…”
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    Journal Article
  10. 10

    QUENCH-LOCA program at KIT on secondary hydriding and results of the commissioning bundle test QUENCH-L0 by Stuckert, J., Große, M., Rössger, C., Klimenkov, M., Steinbrück, M., Walter, M.

    Published in Nuclear engineering and design (01-02-2013)
    “…► Cladding bursts took place during heating at temperatures between 1123 and 1223K. ► Around oxide area at inner cladding surface hydrogen-containing bands…”
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    Journal Article
  11. 11

    Application of thermal hydraulic and severe accident code SOCRAT/V3 to bottom water reflood experiment QUENCH-LOCA-0 by Vasiliev, A.D., Stuckert, J.

    Published in Nuclear engineering and design (01-08-2013)
    “…► QLOCA-0 test simulates a design basis LOCA NPP accident with maximum temperature 1300K. ► Deep understanding of hydraulics and thermal mechanics under…”
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    Journal Article
  12. 12

    Experimental and calculation results of the integral reflood test QUENCH-15 with ZIRLO™ cladding tubes in comparison with results of previous QUENCH tests by Stuckert, J., Birchley, J., Große, M., Jaeckel, B., Steinbrück, M.

    Published in Nuclear engineering and design (01-08-2011)
    “…► Neither breakaway effect nor melt relocation was observed during a test with the ZIRLO™ bundle flooded at 2100 K. ► A noticeable factor of cladding oxidation…”
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  13. 13

    High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys by Steinbrück, M., Birchley, J., Boldyrev, A.V., Goryachev, A.V., Grosse, M., Haste, T.J., Hózer, Z., Kisselev, A.E., Nalivaev, V.I., Semishkin, V.P., Sepold, L., Stuckert, J., Vér, N., Veshchunov, M.S.

    “…This paper gives an overview on the status of knowledge of high-temperature oxidation of the two zirconium alloys Zircaloy-4 and E110 with special emphasis on…”
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    AgInCd control rod failure in the QUENCH-13 bundle test by Sepold, L., Lind, T., Csordás, A. Pintér, Stegmaier, U., Steinbrück, M., Stuckert, J.

    Published in Annals of nuclear energy (01-09-2009)
    “…The QUENCH off-pile experiments performed at the Karlsruhe Research Center are to investigate the high-temperature behavior of Light Water Reactor (LWR) core…”
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  16. 16

    Experimental and post-test calculation results of the integral reflood test QUENCH-12 with a VVER-type bundle by Stuckert, J., Birchley, J., Große, M., Haste, T., Sepold, L., Steinbrück, M.

    Published in Annals of nuclear energy (01-03-2009)
    “…The QUENCH-12 experiment was carried out to investigate the effects of VVER materials (niobium-bearing alloys) and bundle geometry on core reflood, in…”
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  17. 17

    Severe fuel damage experiments performed in the QUENCH facility with 21-rod bundles of LWR-type by Sepold, L., Hering, W., Schanz, G., Scholtyssek, W., Steinbrück, M., Stuckert, J.

    Published in Nuclear engineering and design (01-11-2007)
    “…The objective of the QUENCH experimental program at the Karlsruhe Research Center is to investigate core degradation and the hydrogen source term that results…”
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    Understanding the behaviour of absorber elements in silver–indium–cadmium control rods during PWR severe accident sequences by Dubourg, R., Austregesilo, H., Bals, C., Barrachin, M., Birchley, J., Haste, T., Lamy, J.S., Lind, T., Maliverney, B., Marchetto, C., Pinter, A., Steinbrück, M., Stuckert, J., Trambauer, K., Vimi, A.

    “…In the case of a hypothetical severe accident in a Pressurized Water Reactor (PWR), Silver–Indium–Cadmium (SIC) control rod failure occurs early during the…”
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