Zobrazeno 1 - 10
of 49
pro vyhledávání: '"R.E. Einziger"'
Publikováno v:
Journal of Nuclear Materials. 201:310-319
Hyperstoichiometric U 4 O 9 produced by air-oxidation of LWR spent fuel was studied by ceramography, XRD, TEM, and thermal analysis methods. Several years' oxidation of the spent fuel at 175–195°C completely converted as-irradiated pellet fragment
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::380fd2f9f381c50899dc3176286589ad
https://doi.org/10.1016/0022-3115(93)90187-4
https://doi.org/10.1016/0022-3115(93)90187-4
Publikováno v:
Journal of Nuclear Materials. 190:53-60
Air oxidation tests were conducted on four LWR spent fuels at 175 and 195°C to determine the effects of variations in burnup, gas release, and grain size on oxidation of fuel in a potential repository. Weight gains were measured and samples were exa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a5c9d79611ef7ed3ff8f98a4e9db7d37
https://doi.org/10.1016/0022-3115(92)90075-v
https://doi.org/10.1016/0022-3115(92)90075-v
Publikováno v:
Nuclear Technology. 98:196-206
This paper reports that a methodology is developed to relate U.S. Code of Federal Regulations, Title 10, Part 71 (10CFR71) containment requirements to leak rates for the special case in which the only radioactive species having a potential for escape
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a503d9eb9242ada10a648f1c8d771802
https://doi.org/10.13182/nt92-a34675
https://doi.org/10.13182/nt92-a34675
Autor:
L.E. Thomas, R.E. Einziger
Publikováno v:
Materials Characterization. 28:149-156
The grain boundary oxidation of pressurized-water reactor spent fuel in a dry air atmosphere at 195°C was investigated by light optical and scanning electron microscopy (SEM). The oxidation occurred by U 4 O 9 formation along the grain boundaries an
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b34c9cf8da09935b3062420743551a10
https://doi.org/10.1016/1044-5803(92)90038-j
https://doi.org/10.1016/1044-5803(92)90038-j
Publikováno v:
Journal of Nuclear Materials. 184:117-126
Oxidation of light-water-reactor (LWR) spent fuel fragments in air at 175 °C was investigated by ceramography, X-ray diffractometry, and transmission electron microscopy. Enhanced oxidation of the original fuel pellet edge was observed in a typical
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f353dd925c97d88935fb8ca3e2487abb
https://doi.org/10.1016/0022-3115(91)90502-x
https://doi.org/10.1016/0022-3115(91)90502-x
Publikováno v:
Nuclear Technology. 94:383-393
Multiple samples of moderate-burnup pressurized water reactor (PWR) and boiling water reactor (BWR) spent fuel are oxidized in controlled atmosphere dry baths at 175, 130, and 110{degrees}C. The atmosphere consists of air humidified to a dew point of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2ff2b401544d8756e302fb73844f0c62
https://doi.org/10.13182/nt91-a15816
https://doi.org/10.13182/nt91-a15816
The Chemical Technology (CMT) Division is a diverse technical organization with principal emphases in environmental management and development of advanced energy sources. The Division conducts research and development in three general areas: (1) deve
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4e1c389494a8e3e3e09954aafc163c19
https://doi.org/10.2172/12006
https://doi.org/10.2172/12006
Autor:
W.J. Gray, R.E. Einziger
Hanford N-Reactor spent nuclear fuel (HSNF) may ultimately be placed in a geologic repository for permanent disposal. To determine whether the engineered barrier system that will be designed for emplacement of light-water-reactor (LWR) spent fuel wil
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0180795b6276273cbd981f3eeebab2ad
https://doi.org/10.2172/638266
https://doi.org/10.2172/638266
Publikováno v:
MRS Proceedings. 465
A single-step plasma arc-vitreous ceramic (PAVC) process is described for converting spent nuclear fuel (SNF), SNF sludges, and associated wastes into a vitreous ceramic waste form. This proposed technology is built on extensive experience of nuclear
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::462c9aedf8265f4e65ba78a9b4d9c2b8
https://doi.org/10.1557/proc-465-25
https://doi.org/10.1557/proc-465-25
The Yucca Mountain Site Characterization Project of the US Department of Energy (DOE) is investigating the suitability of the Topopah Spring Tuff at Yucca Mountain, Nevada, for use as a disposal site for spent nuclear fuel and other high-level waste
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6a31845c8d9682d86f8f71310fcb6adf
https://doi.org/10.2172/139726
https://doi.org/10.2172/139726