Zobrazeno 1 - 10
of 35
pro vyhledávání: '"Glen R. Longhurst"'
Publikováno v:
Journal of Nuclear Materials. 456:17-22
Complementary in- and ex-reactor oxidation tests have been performed to evaluate the oxidation and hydrogen absorption performance of Zircaloy-4 (Zr-4) under relatively low partial pressures (300 and 1000 Pa) of water vapor at specified test temperat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dfcbd69b4ed18106e5796b3c3d6bd92f
https://doi.org/10.1016/j.jnucmat.2014.08.053
https://doi.org/10.1016/j.jnucmat.2014.08.053
Autor:
Glen R. Longhurst, Alex Kratville
Publikováno v:
Fusion Science and Technology. 66:385-393
A simple laboratory experiment was constructed to demonstrate in a classroom setting hydrogen permeation under conditions typical of some nuclear applications. The goal was to allow students to fin...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f8736e3bde16d7f952ef4d7dbb0cc700
https://doi.org/10.13182/fst14-801
https://doi.org/10.13182/fst14-801
Publikováno v:
Journal of Nuclear Materials. 437:373-379
The TMIST-2 irradiation experiment was conducted in the Advanced Test Reactor at Idaho National Laboratory to evaluate tritium permeation through Type 316 stainless steel (316 SS). The interior of a 316 SS seamless tube specimen was exposed to a 4He
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d1fdd478a533d09ff0438a6c0af80d1f
https://doi.org/10.1016/j.jnucmat.2013.02.009
https://doi.org/10.1016/j.jnucmat.2013.02.009
Autor:
Satoshi Konishi, S. T. Schuetz, J. P. Sharpe, Kazuyuki Noborio, Teppei Otsuka, Yuji Hatano, Yasushi Yamamoto, Kazunari Katayama, Yasuhisa Oya, Glen R. Longhurst, B. Pawelko, M. Shimada, Masanori Hara, B. Denny, Pattrick Calderoni
Publikováno v:
Journal of Nuclear Materials. 417:1336-1340
The Safety, Tritium and Applied Research facility at the Idaho National Laboratory is a US Department of Energy National User Facility engaged in various aspects of materials research for nuclear applications related to fusion and advanced fission sy
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b125f45314728906be33941e35247049
https://doi.org/10.1016/j.jnucmat.2010.12.303
https://doi.org/10.1016/j.jnucmat.2010.12.303
Autor:
James Cleaver, Glen R. Longhurst
Publikováno v:
Fusion Science and Technology. 54:565-568
Understanding and accounting for interaction of hydrogen isotopes and their oxides with metal surfaces is important for persons working with tritium systems. Reported data from several investigators have shown that the processes of oxidation, adsorpt
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::27062714ed8976cd271bbcd5f7d5d867
https://doi.org/10.13182/fst08-a1879
https://doi.org/10.13182/fst08-a1879
Publikováno v:
Fusion Science and Technology. 48:332-336
The Safety and Tritium Applied Research (STAR) facility has recently been commissioned to investigate tritium-related safety questions for fusion and other technologies. The authorized inventory of tritium is 1.6 grams, the threshold quantity for nuc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bcbe6f0f2daacc72bec2c8d9e86586d3
https://doi.org/10.13182/fst48-331
https://doi.org/10.13182/fst48-331
Autor:
R.J. Pawelko, J. P. Sharpe, Robert A. Anderl, Glen R. Longhurst, S. T. Schuetz, David A. Petti
Publikováno v:
Fusion Science and Technology. 48:243-249
The Safety and Tritium Applied Research (STAR) Facility, a US DOE National User Facility at the Idaho National Engineering and Environmental Laboratory (INEEL), comprises capabilities and infrastructure to support both tritium and non-tritium researc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4672d76e1c9155bb6e1d951d969aceb4
https://doi.org/10.13182/fst48-243
https://doi.org/10.13182/fst48-243
Autor:
Glen R. Longhurst, James Ambrosek
Publikováno v:
Fusion Science and Technology. 48:468-471
The TMAP code has been upgraded to version 7, which includes radioactive decay along with many features implemented in prior versions. Pursuant to acceptance and release for distribution, the code was exercised in a variety of problem types to demons
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c19edb7f9d92daa6786f8e26ff1666a4
https://doi.org/10.13182/fst05-a967
https://doi.org/10.13182/fst05-a967
Autor:
Brad J. Merrill, Glen R. Longhurst
Publikováno v:
Fusion Technology. 39:874-879
The Tritium Migration Analysis Program (TMAP) was an aid in performing safety analyses of fusion systems using combined heat and mass transport calculations. Upgraded to TMAP4, it was verified and validated at the INEEL. The further upgrade of the co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2f4dd0eae5f5d997c3ff75730ddfb993
https://doi.org/10.13182/fst01-a11963349
https://doi.org/10.13182/fst01-a11963349
Autor:
R.J. Pawelko, Glen R. Longhurst, G. Federici, Rion A. Causey, Robert A. Anderl, Anthony A Haasz
Publikováno v:
Journal of Nuclear Materials. :640-644
Plasma-facing components in the International Thermonuclear Experimental Reactor (ITER) will experience high heat loads and intense plasma fluxes of order 1020–1023 particles/m2s. Experiments on Be and W, two of the materials considered for use in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9e56501d7e745789850c3c916090cf2d
https://doi.org/10.1016/s0022-3115(98)00112-3
https://doi.org/10.1016/s0022-3115(98)00112-3