Zobrazeno 1 - 10
of 52
pro vyhledávání: '"Toyoshi Fuketa"'
Publikováno v:
Journal of Nuclear Science and Technology. 48:1369-1376
Ring compression tests were conducted with specimens sampled from high-burnup PWR and BWR fuel cladding segments that had been ruptured, oxidized at 1,405–1,484 K, and quenched in LOCAsimulated experiments. The calculated oxidation amount for cladd
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::59ff6da9d8bfe7a097f326d5a0ab5d38
https://doi.org/10.1080/18811248.2011.9711829
https://doi.org/10.1080/18811248.2011.9711829
Publikováno v:
Journal of Nuclear Materials. 414:303-308
The thermal conductivity formula of fuel pellet which contains the effects of burnup and plutonium (Pu) addition was proposed based on the Klemens’ theory and reported thermal conductivities of unirradiated (U, Pu) O2 and irradiated UO2 pellets. Th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f0e23318c4bfc01d1fd8dde9b258bd50
https://doi.org/10.1016/j.jnucmat.2011.04.020
https://doi.org/10.1016/j.jnucmat.2011.04.020
Publikováno v:
Journal of Nuclear Science and Technology. 47:991-997
In order to clarify the failure mechanism and determine the failure limit of the High-Temperature Gascooled Reactor (HTGR) fuel under reactivity-initiated accident (RIA) conditions, pulse irradiations were performed with unirradiated coated fuel part
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::03543e261716a921109aeabc727bec97
https://doi.org/10.1080/18811248.2010.9711663
https://doi.org/10.1080/18811248.2010.9711663
Publikováno v:
Acta Materialia. 58:3927-3938
Hydrogen embrittlement of zirconium alloys is one of the main causes of the mechanical degradation of the fuel cladding in light water reactors, and has therefore been extensively studied. Although various conjectures have been proposed as the origin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e60cd5df633342678fbbb548a0980de7
https://doi.org/10.1016/j.actamat.2010.03.034
https://doi.org/10.1016/j.actamat.2010.03.034
Publikováno v:
Journal of Nuclear Science and Technology. 47:439-448
In order to evaluate possible effects of initial temperature on the transient fuel behavior, such as cladding deformation and fission gas release, under reactivity-initiated accident conditions, two comparative pulse-irradiation tests were performed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7f10030e952c25caf6671e8ea81e02bf
https://doi.org/10.1080/18811248.2010.9711634
https://doi.org/10.1080/18811248.2010.9711634
Autor:
Toshinori Chuto, Toyoshi Fuketa, Hideo Sasajima, Fumihisa Nagase, Takehiko Nakamura, Tomoyuki Sugiyama
Publikováno v:
Journal of Nuclear Science and Technology. 47:202-210
The radial positions of fission gas release (FGR) in high-burnup fuel pellets were examined after pulseirradiations that simulated reactivity-initiated accident (RIA) conditions in the Nuclear Safety Research Reactor (NSRR). The molar ratio of xenon
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5056e4b1514545d393179457e0afa0c6
https://doi.org/10.1080/18811248.2010.9711946
https://doi.org/10.1080/18811248.2010.9711946
Publikováno v:
Journal of Nuclear Materials. 396:32-42
Two kinds of disk-shaped UO2 samples (4 mm in diameter and 1 mm in thickness) were irradiated in a test reactor up to about 60 and 130 GWd/t, respectively. The microstructures of the samples were investigated by means of optical microscopy, scanning
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f24ff7d3c04842e220328a2ad33fff84
https://doi.org/10.1016/j.jnucmat.2009.10.049
https://doi.org/10.1016/j.jnucmat.2009.10.049
Publikováno v:
Journal of Nuclear Science and Technology. 46:1012-1021
RIA-simulating experiments for high-burnup PWR fuels have been performed in the NSRR, and the stress intensity factor K I at the tip of cladding incipient crack has been evaluated in order to investigate its validity as a PCMI failure threshold under
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ba6943af23e9ee3e74b0e8c6a16f92af
https://doi.org/10.1080/18811248.2009.9711611
https://doi.org/10.1080/18811248.2009.9711611