Oxidation kinetic changes of UO2 by additive addition and irradiation
Source abstract
Abstract
The kinetic changes of air-oxidation of UO2 by additive addition and irradiation were investigated. Several kinds of specimens, such as unirradiated-UO2, simulated-UO2 for spent PWR fuel (SIMFUEL), unirradiated-Gd-doped UO2, irradiated-UO2 and -Gd-doped UO2, were used for these experiments. The oxidation results represented that the kinetic patterns among those samples are remarkably different. It was also revealed that the oxidation kinetics of irradiated-UO2 seems to be more similar to that of unirradiated-Gd-doped UO2 than that of SIMFUEL.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Radioactive element chemistry and processing
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (24)
Show source-provided references
1. Blackburn · J. Phys. Chem. · 1958 · 62 · 90210.1021/j150566a002 ↗
2. Harrison · J. Nucl. Mater. · 1967 · 23 · 12110.1016/0022-3115(67)90058-X ↗
3. Aronson · J Chem. Phys. · 1957 · 27 · 13710.1063/1.1743653 ↗
4. J. Belle (Ed.), Uranium dioxide: properties and nuclear applications, Naval Reactors, Division of Teactor Development, USAEC, 1961
5. Bannister · J. Nucl. Mater. · 1968 · 26 · 17410.1016/0022-3115(68)90069-X ↗
6. Thomas · J. Nucl. Mater. · 1991 · 184 · 11710.1016/0022-3115(91)90502-X ↗
7. Taylor · J. Nucl. Mater. · 1992 · 189 · 11610.1016/0022-3115(92)90425-K ↗
8. K.J. Schneider, S.J. Mitchell, A.B. Johnson Jr., Proc. 3rd Int. Conf. on High Level Radioactive Waste Management, Las Vegas, 1992, p. 1159
9. Wasywich · Nucl. Technol. · 1993 · 104 · 30910.13182/NT93-A34893 ↗
10. McEachern · J. Nucl. Mater. · 1998 · 254 · 8710.1016/S0022-3115(97)00343-7 ↗
11. RSIC Computer code collection, ORIGEN2.1: Isotope generation and depletion code matrix exponential method, CCC-371, 1991
12. Choi · J. Nucl. Mater. · 1996 · 230 · 25010.1016/0022-3115(96)80022-5 ↗
13. Thomas · J. Nucl. Mater. · 1993 · 201 · 31010.1016/0022-3115(93)90187-4 ↗
14. Campbell · Nucl. Technol. · 1989 · 85 · 16010.13182/NT89-A34238 ↗
15. Boase · Nucl. Technol. · 1977 · 32 · 6010.13182/NT77-A31738 ↗
16. Hastings · J. Am. Ceram. Soc. · 1986 · 69 · C1610.1111/j.1151-2916.1986.tb04723.x ↗
17. J. Schmets, Pretreatment of irradiated fuels Quartly report 14, July 1-September 30, 1963. EURAEC-884,US–Euratom Joint Research and Development Program 1963
18. C.S. Olsen, EG&G Idaho, Report, NUREG/CR-4074, EGG-2364, 1985
19. Olsen · Nucl. Eng. Design · 1985 · 89 · 5110.1016/0029-5493(85)90142-6 ↗
20. Harrison · J. Nucl. Mater. · 1970 · 36 · 11610.1016/0022-3115(70)90070-X ↗
21. E.R. Gilbert, G.D. White, C.A. Knox, Proc. Int. Workshop on Irradiated Fuel Storage: Operating Experience and Development Programs, 17-18 October 1984, Toronto, ON, Canada, 1984, p. 551
22. Campbell · Nucl. Technol. · 1989 · 84 · 18210.13182/NT89-A34186 ↗
23. Kim · J. Korean Nucl. Soc. · 1997 · 29 · 93
24. L.E. Thomas, J.M. McCarthy, E.R. Gilbert, Proc. 3rd Int. Spent Fuel Storage, Tech. Symp., CONF-860417, Seattle, WA, 1986, p. W-40