On the nuclear oxide fuel densification, swelling and thermal re-sintering
A method of calculating the fuel densification and swelling as a result of only the initial fuel porosity has been developed. Well-characterized UO 2 fuel pellets, from the Romanian CANDU type fuel fabrication route, were used to fit the specific pore volume distribution resulted from the sintering...
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| Published in | Journal of nuclear materials Vol. 302; no. 2; pp. 109 - 124 |
|---|---|
| Main Authors | , , |
| Format | Journal Article |
| Language | English |
| Published |
Amsterdam
Elsevier B.V
2002
Elsevier |
| Subjects | |
| Online Access | Get full text |
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| Abstract | A method of calculating the fuel densification and swelling as a result of only the initial fuel porosity has been developed. Well-characterized UO
2 fuel pellets, from the Romanian CANDU type fuel fabrication route, were used to fit the specific pore volume distribution resulted from the sintering process to a lognormal distribution function and thermal re-sintering tests up to 280 h at 1700 °C were done to fit the coefficients of vacancies diffusion and the self-diffusion of uranium, required by the model. Careful analyses proved that the irradiation-induced resolution is strongly dependent of the hydrostatic pressure and a corrected formula has been proposed. Analyses of the time evolution of the pore size distribution during re-sintering tests and annealing tests similar with some as described in the open literature were also done. |
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| AbstractList | A method of calculating the fuel densification and swelling as a result of only the initial fuel porosity has been developed. Well-characterized UO
2 fuel pellets, from the Romanian CANDU type fuel fabrication route, were used to fit the specific pore volume distribution resulted from the sintering process to a lognormal distribution function and thermal re-sintering tests up to 280 h at 1700 °C were done to fit the coefficients of vacancies diffusion and the self-diffusion of uranium, required by the model. Careful analyses proved that the irradiation-induced resolution is strongly dependent of the hydrostatic pressure and a corrected formula has been proposed. Analyses of the time evolution of the pore size distribution during re-sintering tests and annealing tests similar with some as described in the open literature were also done. |
| Author | Paraschiv, M.C. Paraschiv, A. Grecu, V.V. |
| Author_xml | – sequence: 1 givenname: M.C. surname: Paraschiv fullname: Paraschiv, M.C. email: mariusparaschiv@mail.rtns.ro organization: Institute for Nuclear Research, P.O. Box 78, R-0300 Pitesti, Romania – sequence: 2 givenname: A. surname: Paraschiv fullname: Paraschiv, A. organization: Institute for Nuclear Research, P.O. Box 78, R-0300 Pitesti, Romania – sequence: 3 givenname: V.V. surname: Grecu fullname: Grecu, V.V. organization: Faculty of Physics, University of Bucharest, P.O. Box MG-11 Bucharest, Romania |
| BackLink | http://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=13666160$$DView record in Pascal Francis |
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| CODEN | JNUMAM |
| CitedBy_id | crossref_primary_10_1016_j_mechmat_2005_11_004 crossref_primary_10_1016_j_jeurceramsoc_2015_07_010 crossref_primary_10_1111_jace_15741 crossref_primary_10_1016_j_jnucmat_2018_03_046 crossref_primary_10_1016_j_matchemphys_2012_10_003 crossref_primary_10_1016_j_net_2021_02_019 |
| Cites_doi | 10.1080/14786437508228092 10.1016/0022-3115(71)90201-7 10.1016/0022-3115(76)90061-1 10.1080/14786437108217391 10.1016/0022-3115(87)90025-0 10.1080/14786436908216311 10.1016/0022-3115(75)90099-9 10.1016/0022-3115(88)90003-7 10.1080/14786435908243264 10.1016/0022-3115(71)90044-4 10.13182/NSE69-A20676 10.1098/rsta.1991.0062 10.1063/1.38335 10.1016/0022-3115(82)90432-9 10.1016/0022-3697(61)90054-3 10.1001/jama.250.14.1841b 10.1063/1.1736107 10.1016/0022-3115(85)90437-4 10.1016/S0022-3115(97)00039-1 10.1016/0022-3115(87)90024-9 10.1016/0022-3115(78)90454-3 10.1016/0022-3115(80)90008-2 10.1016/0022-3115(69)90047-6 10.13182/NT70-A28805 10.1016/0022-3115(80)90288-3 10.1016/0022-3115(83)90176-9 10.1016/0022-3115(82)90414-7 10.3327/jnst.35.796 10.1016/0022-3115(71)90075-4 10.2172/7343826 10.1080/0267257X.1996.9964419 10.1016/0022-3115(76)90273-7 10.1016/0022-3115(91)90401-R |
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| Keywords | F0700 P1000 Density measurement Swelling Fuel densification Oxides Nuclear fuel Uranium oxide Resintering Fuel pellet |
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| Snippet | A method of calculating the fuel densification and swelling as a result of only the initial fuel porosity has been developed. Well-characterized UO
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| SubjectTerms | Applied sciences Energy Exact sciences and technology Fuels Nuclear fuels Preparation and processing of nuclear fuels |
| Title | On the nuclear oxide fuel densification, swelling and thermal re-sintering |
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