Search Results - "Pintsuk, G."

Refine Results
  1. 1

    Thermal shock tests to qualify different tungsten grades as plasma facing material by Wirtz, M, Linke, J, Loewenhoff, Th, Pintsuk, G, Uytdenhouwen, I

    Published in Physica scripta (20-02-2016)
    “…The electron beam device JUDITH 1 was used to establish a testing procedure for the qualification of tungsten as plasma facing material. Absorbed power…”
    Get full text
    Journal Article
  2. 2

    Impact of microstructure on the plasma performance of industrial and high-end tungsten grades by Pintsuk, G., Loewenhoff, Th

    Published in Journal of nuclear materials (01-07-2013)
    “…Tungsten and tungsten alloys are actually the primary choice as plasma facing materials for future fusion reactors. Thereby, the material’s response to the…”
    Get full text
    Journal Article
  3. 3

    Cracking failure study of ITER-reference tungsten grade under single pulse thermal shock loads at elevated temperatures by Hirai, T., Pintsuk, G., Linke, J., Batilliot, M.

    Published in Journal of nuclear materials (15-06-2009)
    “…Crack formation in an ITER-reference tungsten grade was examined under single thermal shock loading. Typically two sorts of cracks, major cracks and…”
    Get full text
    Journal Article Conference Proceeding
  4. 4

    Thermal shock characterization of tungsten deformed in two orthogonal directions by Pintsuk, G., Prokhodtseva, A., Uytdenhouwen, I.

    Published in Journal of nuclear materials (01-10-2011)
    “…The increasing importance of tungsten and tungsten alloys for future nuclear fusion facilities and reactors requires an increasing understanding of the…”
    Get full text
    Journal Article Conference Proceeding
  5. 5

    DEMO design activity in Europe: Progress and updates by Federici, G., Bachmann, C., Barucca, L., Biel, W., Boccaccini, L., Brown, R., Bustreo, C., Ciattaglia, S., Cismondi, F., Coleman, M., Corato, V., Day, C., Diegele, E., Fischer, U., Franke, T., Gliss, C., Ibarra, A., Kembleton, R., Loving, A., Maviglia, F., Meszaros, B., Pintsuk, G., Taylor, N., Tran, M.Q., Vorpahl, C., Wenninger, R., You, J.H.

    Published in Fusion engineering and design (01-11-2018)
    “…This paper describes the progress of the DEMO Design Activities in Europe and particularly the work done to address critical design integration issues that…”
    Get full text
    Journal Article
  6. 6

    Thermo-mechanical and thermal shock characterization of potassium doped tungsten by Pintsuk, G., Uytdenhouwen, I.

    “…One potential plasma facing material candidate for future nuclear fusion facilities and reactors like ITER and especially DEMO is potassium doped tungsten,…”
    Get full text
    Journal Article
  7. 7

    Recrystallization and composition dependent thermal fatigue response of different tungsten grades by Pintsuk, G., Antusch, S., Weingaertner, T., Wirtz, M.

    “…Industrial pure tungsten grades, manufactured by using a variety of manufactured techniques, are available worldwide in many different types of semifinished…”
    Get full text
    Journal Article
  8. 8

    Tungsten and CFC degradation under combined high cycle transient and steady state heat loads by Loewenhoff, Th, Linke, J., Pintsuk, G., Thomser, C.

    Published in Fusion engineering and design (01-08-2012)
    “…► Tungsten and CFC were subjected to transient high cycle heat loads. ► Tungsten showed fatigue damage (roughening, cracking, melting). ► Roughening occurred…”
    Get full text
    Journal Article
  9. 9

    Comparison of thermal shock damages induced by different simulation methods on tungsten by Wirtz, M., Linke, J., Pintsuk, G., Singheiser, L., Zlobinski, M.

    Published in Journal of nuclear materials (01-07-2013)
    “…In this work two simulation methods for transient events on tungsten are compared. ELM-like thermal shock tests were performed with the electron beam device…”
    Get full text
    Journal Article
  10. 10

    Materials for DEMO and reactor applications-boundary conditions and new concepts by Coenen, J W, Antusch, S, Aumann, M, Biel, W, Du, J, Engels, J, Heuer, S, Houben, A, Hoeschen, T, Jasper, B, Koch, F, Linke, J, Litnovsky, A, Mao, Y, Neu, R, Pintsuk, G, Riesch, J, Rasinski, M, Reiser, J, Rieth, M, Terra, A, Unterberg, B, Weber, Th, Wegener, T, You, J-H, Linsmeier, Ch

    Published in Physica scripta (20-02-2016)
    “…DEMO is the name for the first stage prototype fusion reactor considered to be the next step after ITER towards realizing fusion. For the realization of fusion…”
    Get full text
    Journal Article
  11. 11

    Atmospheric plasma spraying of functionally graded steel/tungsten layers for the first wall of future fusion reactors by Heuer, S., Matějíček, J., Vilémová, M., Koller, M., Illkova, K., Veverka, J., Weber, Th, Pintsuk, G., Coenen, J.W., Linsmeier, Ch

    Published in Surface & coatings technology (25-05-2019)
    “…Functionally graded steel/tungsten layers may be used as interlayers in the first wall of future fusion reactors to balance thermally-induced stress peaks in…”
    Get full text
    Journal Article
  12. 12

    Thermal shock of tungsten carbide in plasma-facing conditions by Humphry-Baker, S.A., Smith, G.D.W., Pintsuk, G.

    Published in Journal of nuclear materials (01-10-2019)
    “…Tungsten carbide (WC) has been found to have higher resistance to plasma-induced thermal shock compared to rolled tungsten. The electron beam device JUDITH 1…”
    Get full text
    Journal Article
  13. 13

    Overview of challenges and developments in joining tungsten and steel for future fusion reactors by Heuer, S, Coenen, J W, Pintsuk, G, Mat jí ek, J, Vilémová, M, Linsmeier, Ch

    Published in Physica scripta (01-01-2020)
    “…In future fusion reactors, the blanket is foreseen to remove heat from the reactor and enclose material to breed tritium. While the blanket structure is made…”
    Get full text
    Journal Article
  14. 14

    Additive manufacturing of high density pure tungsten by electron beam melting by Dorow-Gerspach, D., Kirchner, A., Loewenhoff, Th, Pintsuk, G., Weißgärber, T., Wirtz, M.

    Published in Nuclear materials and energy (01-09-2021)
    “…[Display omitted] •Nearly-crack free bulk material with theoretical density above 99% was produced.•Transition regime between sintering, partial, and complete…”
    Get full text
    Journal Article
  15. 15

    Qualification and post-mortem characterization of tungsten mock-ups exposed to cyclic high heat flux loading by Pintsuk, G., Bobin-Vastra, I., Constans, S., Gavila, P., Rödig, M., Riccardi, B.

    Published in Fusion engineering and design (01-10-2013)
    “…•We characterize tungsten mono-block components after exposure to ITER relevant heat loads.•We qualify the manufacturing technology, i.e., hot isostatic…”
    Get full text
    Journal Article
  16. 16

    Thermal shock response of deformed and recrystallised tungsten by Wirtz, M., Cempura, G., Linke, J., Pintsuk, G., Uytdenhouwen, I.

    Published in Fusion engineering and design (01-10-2013)
    “…•Microstructure has a strong influence on the mechanical properties of tungsten.•Threshold values vary with microstructure by a factor of 2.•Thermal shock…”
    Get full text
    Journal Article
  17. 17

    Aiming at understanding thermo-mechanical loads in the first wall of DEMO: Stress–strain evolution in a Eurofer-tungsten test component featuring a functionally graded interlayer by Heuer, S., Weber, Th, Pintsuk, G., Coenen, J.W., Matejicek, J., Linsmeier, Ch

    Published in Fusion engineering and design (01-10-2018)
    “…For the future fusion demonstration power plant, DEMO, several blanket designs are currently under consideration. Despite geometric and operational…”
    Get full text
    Journal Article
  18. 18

    Development of Nanostructured Tungsten Based Materials Resistant to Recrystallization and/or Radiation Induced Embrittlement by Kurishita, H., Arakawa, H., Matsuo, S., Sakamoto, T., Kobayashi, S., Nakai, K., Pintsuk, G., Linke, J., Tsurekawa, S., Yardley, V., Tokunaga, K., Takida, T., Katoh, M., Ikegaya, A., Ueda, Y., Kawai, M., Yoshida, N.

    Published in MATERIALS TRANSACTIONS (01-01-2013)
    “…Mitigation of embrittlement caused by recrystallization and radiation is the key issue of tungsten (W) based materials for use in the advanced nuclear system…”
    Get full text
    Journal Article
  19. 19

    Technology readiness assessment of materials for DEMO in-vessel applications by Richardson, M., Gorley, M., Wang, Y., Aiello, G., Pintsuk, G., Gaganidze, E., Richou, M., Henry, J., Vila, R., Rieth, M.

    Published in Journal of nuclear materials (01-07-2021)
    “…•A technology readiness assessment was carried out on key materials under development within EUROfusion.•Assessed materials include those for structural, high…”
    Get full text
    Journal Article
  20. 20

    Thermal shock behavior of potassium doped and rhenium added tungsten alloys by Nogami, S, Pintsuk, G, Matsui, K, Watanabe, S, Wirtz, M, Loewenhoff, T, Hasegawa, A

    Published in Physica scripta (01-01-2020)
    “…High ductile-to-brittle transition temperature, recrystallization-induced embrittlement, and neutron-irradiation-induced embrittlement are potential drawbacks…”
    Get full text
    Journal Article