Zobrazeno 1 - 10
of 49
pro vyhledávání: '"A. J. MACHIELS"'
Publikováno v:
Nuclear Engineering and Design. 324:250-259
The end-of-life (EOL) fuel rod internal pressure (RIP) is a critical parameter for assessing the performance of spent fuel during dry storage and transportation. At issue are several potential degradation mechanisms that are strongly dependent on rod
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7e289e827db6bd98926dc8d0f2d61f2f
https://doi.org/10.1016/j.nucengdes.2017.09.002
https://doi.org/10.1016/j.nucengdes.2017.09.002
Autor:
Albert J. Machiels, C. Mallet, Q. Auzoux, Suresh Yagnik, Kimberly Colas, P. Bouffioux, B. Bourdiliau, N. Mozzani
Publikováno v:
Journal of Nuclear Materials. 494:114-126
Precipitation of radial hydrides in zirconium-based alloy cladding concomitant with the cooling of spent nuclear fuel during dry storage can potentially compromise cladding integrity during its subsequent handling and transportation. This paper inves
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d612912e893e54abf15055ffe6b077e5
https://doi.org/10.1016/j.jnucmat.2017.07.022
https://doi.org/10.1016/j.jnucmat.2017.07.022
Autor:
Albert J. Machiels, James H. Clarke, Steven Krahn, Andrew Sowder, Bethany L. Smith, Allen Croff
Publikováno v:
Nuclear Technology. 185:192-207
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::de43f28f85b212d9a731a921c5d11f6c
https://doi.org/10.13182/nt13-64
https://doi.org/10.13182/nt13-64
Publikováno v:
Nuclear Technology. 185:39-56
Pressurized water reactor (PWR) assembly reactivity distributions are inferred from ~600 in-core flux maps taken during 44 cycles of operation of the Catawba and McGuire nuclear power plants. The r...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3080eb3602af3f74ebc31a0382d42cb3
https://doi.org/10.13182/nt13-31
https://doi.org/10.13182/nt13-31
Publikováno v:
Nuclear Technology. 185:57-70
The Electric Power Research Institute (EPRI) has sponsored the development of a set of benchmarks that can be used to quantify the bias and uncertainty in computed reactivity decrements due to burn...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2d6dfbb904334a5c8f5d88bf99186883
https://doi.org/10.13182/nt13-28
https://doi.org/10.13182/nt13-28
Autor:
Albert J. Machiels, Alan H. Wells
Publikováno v:
Nuclear Technology. 179:180-188
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::75ffcb68e650de7a15c9cbdfa8f1b333
https://doi.org/10.13182/nt12-a14090
https://doi.org/10.13182/nt12-a14090
Autor:
Albert J. Machiels, Alan H. Wells
Publikováno v:
Nuclear Technology. 176:387-394
According to the U.S. Nuclear Regulatory Commission’s guidance based on concerns for potential channeling of neutrons between absorber particles, the criticality safety of transportation systems sh...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2158372bccf1f591201aec89852c6614
https://doi.org/10.13182/nt11-a13315
https://doi.org/10.13182/nt11-a13315
Autor:
A. A. Dykes, A. J. Machiels
Publikováno v:
Packaging, Transport, Storage & Security of Radioactive Material. 21:51-61
A probabilistic risk assessment (PRA) quantifies the frequency of criticality accidents during railroad transport of spent nuclear fuel casks (SFCs) in the USA. It evaluates the likelihood that undetected errors in fuel selection and/or fuel handling
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1e002eaa7c8bd85417d89e4b860b1670
https://doi.org/10.1179/174650910x12665760844396
https://doi.org/10.1179/174650910x12665760844396
Autor:
J. Y. R. Rashid, A. J. Machiels
Publikováno v:
Packaging, Transport, Storage & Security of Radioactive Material. 16:211-218
Recent studies on the long-term behaviour of high-burnup spent fuel have shown that, under normal conditions of storage, challenges to cladding integrity from various postulated damage mechanisms, such as delayed hydride cracking, stress-corrosion cr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bfa510172369bb84f3f96e7b5d77c534
https://doi.org/10.1179/174650905775295297
https://doi.org/10.1179/174650905775295297
Publikováno v:
Journal of Nuclear Materials. 270:65-73
In order to better understand the behavior of irradiated UO 2 , six fuel rods containing fuel pellets fabricated by wet and dry processes were irradiated under various power histories in the BR-3 PWR (Mol, Belgium). Subsequent to the irradiation, ext
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::704ea2007ff992e52616d88d37f1ae72
https://doi.org/10.1016/s0022-3115(98)00896-4
https://doi.org/10.1016/s0022-3115(98)00896-4