Search Results - "Puigh, R.J."

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  1. 1

    Near-field performance assessment for a low-activity waste glass disposal system: laboratory testing to modeling results by McGrail, B.P., Bacon, D.H., Icenhower, J.P., Mann, F.M., Puigh, R.J., Schaef, H.T., Mattigod, S.V.

    Published in Journal of nuclear materials (01-09-2001)
    “…Reactive chemical transport simulations of glass corrosion and radionuclide release from a low-activity waste (LAW) disposal system were conducted out to times…”
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    Journal Article
  2. 2

    Irradiation creep of 11Cr–0.5Mo–2W,V,Nb ferritic–martensitic, modified 316, and 15Cr–20Ni austenitic S.S. irradiated in FFTF to 103–206 dpa by Uehira, A, Mizuta, S, Ukai, S, Puigh, R.J

    Published in Journal of nuclear materials (01-12-2000)
    “…The irradiation creep of 11Cr–0.5Mo–2W–0.2V–0.05Nb ferritic–martensitic (PNC-FMS), modified 316 (PNC316) and 15Cr–20Ni base austenitic S.S. were determined by…”
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    Journal Article
  3. 3

    Swelling, irradiation creep and growth of pure rhenium irradiated with fast neutrons at 1030–1330°C by Garner, F.A, Toloczko, M.B, Greenwood, L.R, Eiholzer, C.R, Paxton, M.M, Puigh, R.J

    Published in Journal of nuclear materials (01-12-2000)
    “…This paper discusses the results of two series of experiments conducted on pure hcp rhenium in the EBR-II and FFTF fast reactors. In FFTF, density change data…”
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    Journal Article
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