Zobrazeno 1 - 10
of 108
pro vyhledávání: '"Clive T. Walker"'
Publikováno v:
Journal of Nuclear Materials. 513:310-345
Gaseous fission product generation, transport, and release can have a large impact on nuclear fuel performance, degrading fuel and fuel–cladding gap properties. Over the past several decades much progress has been made in understanding the key mech
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b66b19aa8a6fba40e0ecd6508a5ce565
https://doi.org/10.1016/j.jnucmat.2018.08.019
https://doi.org/10.1016/j.jnucmat.2018.08.019
Autor:
Matthias I. Horvath, Johannes Bertsch, Renato Restani, Clive T. Walker, Matthias Martin, Armin Hermann, W. Goll, D. Gavillet
Publikováno v:
Journal of Nuclear Materials. 481:88-100
Post-irradiation examination results are presented for UO 2 fuel from a PWR fuel rod that had been irradiated to an average burn-up of 105 MWd/kgHM and showed high fission gas release of 42%. The radial distribution of xenon and the partitioning of f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6ad61e1bf9a51c3db150f7381f40091c
https://doi.org/10.1016/j.jnucmat.2016.08.023
https://doi.org/10.1016/j.jnucmat.2016.08.023
Autor:
M. Sheindlin, Claudio Ronchi, A. Sasahara, R.J.M. Konings, T. Sonoda, M. Kinoshita, Vincenzo V. Rondinella, D. Staicu, D. Papaioannou, Clive T. Walker
Publikováno v:
Journal of Nuclear Materials. 453(1-3):259-268
The thermal diffusivity of reactor irradiated (U,Gd)O 2 fuels has been measured, for burn-ups from 33 to 97 GWd tHM − 1 and for irradiation temperatures from 670 to 1580 K. Measurements under thermal annealing cycles were performed in order to inve
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8170f8fc09f27b7f280ce1f2a5e13957
Publikováno v:
Journal of Nuclear Materials 452(2014), 166-172
Experimental results for the Xe depletion in the matrix of high burn-up fuel are presented from the High Burnup Rim Project (HBRP). In this project a number of UO 2 fuel discs with 235 U enrichment of 25.8 wt.% were irradiated. The Xe content of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::20b02e93874f43dd19586d3e42e10475
https://doi.org/10.1016/j.jnucmat.2014.05.009
https://doi.org/10.1016/j.jnucmat.2014.05.009
Autor:
S. Bremier, Vincenzo V. Rondinella, D. Papaioannou, Clive T. Walker, S. Van Winckel, P. Van Uffelen, Dario Manara, P.D.W. Bottomley, Jean-Paul Glatz, P. Pöml
Publikováno v:
Annals of Nuclear Energy. 65:345-356
With the current situation in Japan one should examine previous research into severe accidents and the current state of European severe accident research to assess what are the priorities for research for existing and future nuclear reactors. The Eur
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cbc2a4d56611c5fe066a820f8920c139
https://doi.org/10.1016/j.anucene.2013.11.012
https://doi.org/10.1016/j.anucene.2013.11.012
Autor:
Jasper Berndt, Clive T. Walker, Marion Grange, P. Pöml, R. Hasnaoui, Alexander A. Nemchin, P.D.W. Bottomley, Raúl O.C. Fonseca, Thorsten Geisler, Boris E. Burakov
Publikováno v:
Journal of Nuclear Materials. 439:51-56
U isotope data measured on real fragments of the Chernobyl nuclear fuel included in zircon crystals crystallised from the Chernobyl “lava” are presented for the first time. The U isotope data show no anomalies and lie within the expected burnup v
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b1a14a30e27320f3f46ff5143cbf5152
https://doi.org/10.1016/j.jnucmat.2013.03.031
https://doi.org/10.1016/j.jnucmat.2013.03.031
Autor:
Lelio Luzzi, Paul Van Uffelen, Wim Haeck, P. Botazzoli, S. Bremier, Clive T. Walker, A. Schubert, W. Goll
Publikováno v:
Journal of Nuclear Materials. 419:329-338
The TRANSURANUS burn-up model (TUBRNP) calculates the local concentration of the actinides, the main fission products, and 4He as a function of the radial position across a fuel rod. In this paper, the improvements in the helium production model as w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::95df883ba7e7e248995658398abe9ae1
https://doi.org/10.1016/j.jnucmat.2011.05.040
https://doi.org/10.1016/j.jnucmat.2011.05.040
Autor:
D. Papaioannou, Cedric Cozzo, Vincenzo V. Rondinella, Giorgio Pagliosa, Clive T. Walker, Stephan Bremier, D. Staicu, A. Sasahara
Publikováno v:
Journal of Nuclear Materials. 412:129-137
New thermal diffusivity data for homogeneous SBR and heterogeneous MIMAS and OCOM MOX fuels are reported. No significant difference between the thermal diffusivity of the homogeneous and heterogeneous fuels was found at the burn-up up to 44 MWd/kgHM.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::be2f10aea383d49083fd829525331bd6
https://doi.org/10.1016/j.jnucmat.2011.02.042
https://doi.org/10.1016/j.jnucmat.2011.02.042
Publikováno v:
Journal of Nuclear Materials. 393:212-223
The results of a wide-ranging post-irradiation study of a PWR nuclear fuel by secondary ion mass spectrometry are presented. The average cross-section burn-up and the radial burn-up profile were determined from the radial distributions of one or more
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::30f2a0b494f716e507d7f03360d46e7f
https://doi.org/10.1016/j.jnucmat.2009.06.017
https://doi.org/10.1016/j.jnucmat.2009.06.017
Publikováno v:
Applied Surface Science. 255:1323-1326
A UO2 single crystal implanted with 83Kr was analysed with a shielded Cameca IMS 6f SIMS. The main objective was to develop measurement and quantification procedures for krypton in irradiated nuclear fuel. It was found that good quality 83Kr+ depth p
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a1cd3bdef4e394ae0a8a681ce3e62cee
https://doi.org/10.1016/j.apsusc.2008.05.263
https://doi.org/10.1016/j.apsusc.2008.05.263