Search Results - "STORAI, S"

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  1. 1

    HyPer-QuarCh II: A laboratory-scale device for hydrogen isotopes permeation experiments by Candido, L., Alberghi, C., Antonelli, A., Bassini, S., Piccioni, M., Storai, S., Testoni, R., Utili, M., Zucchetti, M.

    Published in Fusion engineering and design (01-11-2021)
    “…•A new laboratory-scale facility for hydrogen isotopes permeation experiments in static LiPb is presented.•The facility aims to characterize hydrogen isotopes…”
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    Journal Article
  2. 2

    Grain size reduction strategies on Eurofer by Pilloni, L., Cristalli, C., Tassa, O., Salvatori, I., Storai, S.

    Published in Nuclear materials and energy (01-12-2018)
    “…•Double Normalization effective to reduce PAGS (Prior Austenite Grain Size).•Asymmetric Hot Rolling effective to refine Grain Size prior the multiple…”
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    Journal Article
  3. 3

    Influence of the manufacturing heat cycles on the CuCrZr properties by Merola, M., Orsini, A., Visca, E., Libera, S., Moreschi, L.F., Storai, S., Panella, B., Campagnoli, E., Ruscica, G., Bosco, C.

    Published in Journal of nuclear materials (01-12-2002)
    “…The use of CuCrZr in the proper aged condition is hindered by the manufacturing process of components, which may involve several high temperature steps, which…”
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    Journal Article
  4. 4

    Cyclic testing of shear keys for the ITER magnet system by Rossi, P., Moreschi, L.F., Pizzuto, A., Storai, S., Sborchia, C.

    Published in Fusion engineering and design (01-11-2005)
    “…Shear keys are to be used to support the out-of-plane loading of the toroidal field (TF) coils during a plasma pulse in ITER. At the inner intercoil structures…”
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    Journal Article Conference Proceeding
  5. 5

    A remotely operated FIMEC apparatus for the mechanical characterization of neutron irradiated materials by Donato, A, Gondi, P, Montanari, R, Moreschi, L, Sili, A, Storai, S

    Published in Journal of nuclear materials (01-10-1998)
    “…From Flat-top Cylinder Indenter for Mechanical Characterization (FIMEC) test yield stress and tensile strength can be obtained. Results regarding different…”
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    Journal Article
  6. 6

    Mechanical characterisation of fusion materials by indentation test by Riccardi, B, Montanari, R, Moreschi, L.F, Sili, A, Storai, S

    Published in Fusion engineering and design (01-11-2001)
    “…FIMEC is an indentation test, which permits the evaluation of yield and ultimate tensile stress and to draw indication about the ductile to brittle transition…”
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    Journal Article Conference Proceeding
  7. 7

    Full scale electrical insulation coating development by Moreschi, L.F., Rossi, P., Agostini, M., Storai, S., Peacock, A.T.

    Published in Fusion engineering and design (01-09-2003)
    “…A de-mountable mechanical system has been designed by ITER-IT for the attachment and the remote handling of the blanket modules. The modules are attached to…”
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    Journal Article Conference Proceeding
  8. 8

    Mechanical and electrical tests on the attachment keys for the divertor vertical target by Moreschi, L.F, Pizzuto, A, Agostini, M, Storai, S, Riccardi, B, Merola, M

    Published in Fusion engineering and design (01-10-2001)
    “…The European divertor outboard channel provides the use of adjustable keys for the attachment system of the ITER divertor components, in particular vertical…”
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    Journal Article Conference Proceeding
  9. 9

    A remotely operated FIMEC apparatus for the mechanical characterization of neutron irradiated materials by Donato, A, Gondi, P, Montanari, R, Moreschi, L, Sili, A, Storai, S

    Published in Journal of nuclear materials (26-10-1997)
    “…From Flat-top Cylinder Indenter for Mechanical Characterization (FIMEC) test yield stress and tensile strength can be obtained. Results regarding different…”
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    Journal Article
  10. 10
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