Zobrazeno 1 - 10
of 94
pro vyhledávání: '"R.J. Puigh"'
Autor:
Herbert T. Schaef, R.J. Puigh, B. P. McGrail, Jonathan P. Icenhower, Shas V. Mattigod, F.M. Mann, Diana H. Bacon
Publikováno v:
Journal of Nuclear Materials. 298:95-111
Reactive chemical transport simulations of glass corrosion and radionuclide release from a low-activity waste (LAW) disposal system were conducted out to times in excess of 20 000 yr with the subsurface transport over reactive multiphases (STORM) cod
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c712cdf1cecea196618a45ee3a7b3248
https://doi.org/10.1016/s0022-3115(01)00576-1
https://doi.org/10.1016/s0022-3115(01)00576-1
Publikováno v:
Journal of Nuclear Materials. :396-399
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 the gas pressurized capsule irradiation test using MOTA in FFTF. The pressurized capsules a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1c0d881f4237d49aa7ff15c82a4a412e
https://doi.org/10.1016/s0022-3115(00)00079-9
https://doi.org/10.1016/s0022-3115(00)00079-9
An empirical in-reactor creep equation has been developed for 20% cold worked 316SS. This equation is based upon creep data obtained predominately from pressurized tube specimens irradiated in the Experimental Breeder Reactor EBR-II at specific irrad
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::007f3987cc6a8fad8902cbb32db4784d
https://doi.org/10.1520/stp34341s
https://doi.org/10.1520/stp34341s
Autor:
Francis A. Garner, R.J. Puigh, C.R. Eiholzer, Margaret L. Hamilton, Mychailo B. Toloczko, Duncan, A. S. Kumar
This report discusses thin-walled pressurized tubes which have been developed for measurement of thermal creep and irradiation creep. Miniaturization of these tubes allows more tests to be conducted in the limited reactor space available and decrease
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fb035d0fd0f10f739567c141d57c4f71
https://doi.org/10.1520/stp23963s
https://doi.org/10.1520/stp23963s
Autor:
R.J. Puigh, Francis A. Garner
Publikováno v:
Journal of Nuclear Materials. :577-580
The irradiation creep and swelling at 400–750°C of the fusion heats of PCA, HT9 and 9Cr-lMo were studied using pressurized tubes irradiated in the Fast Flux Test Facility (FFTF). At temperatures
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f4c3cb2977d981058d691b74d8ce276c
https://doi.org/10.1016/0022-3115(91)90153-x
https://doi.org/10.1016/0022-3115(91)90153-x
Autor:
R.J. Puigh, Frank A. Garner
Titanium additions tend to suppress swelling of stainless steel alloy AISI 316 in the annealed condition. Evidence is presented to show that a similar effect occurs in the cold-worked condition in both EBR-II and FFTF. The titanium-modified steels ow
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::94066ada48546b2ff3fc15f2ba4f91aa
https://doi.org/10.1520/stp33815s
https://doi.org/10.1520/stp33815s
Autor:
N. Abraham, P.J. Maziasz, Margaret L. Hamilton, Francis A. Garner, Gerald Duane Johnson, R.J. Puigh, W.J.S. Yang
Austenitic stainless steels are used for core component materials in liquid metal cooled reactors (LMRs). To extend the lifetime of LMR fuel assemblies, considerable effort was expended by the US breeder materials program to find ways to minimize rad
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d59b2baefb4acb829cb27fbcf753fd5d
https://doi.org/10.1520/stp24576s
https://doi.org/10.1520/stp24576s
Autor:
R.J. Puigh
This document describes the tasks included in the Hanford Low-Activity Tank Waste Performance Assessment activity though the close of the project in 2028. Near-term (2001-2006) tasks are described in detail, while tasks further in the future are simp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::125c362c760bbe2c1a84b16b29300dc7
https://doi.org/10.2172/804248
https://doi.org/10.2172/804248
The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c2f38059e1769a77779070d977570597
https://doi.org/10.2172/409923
https://doi.org/10.2172/409923