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Volumn 807, Issue , 2004, Pages 83-88

The oxidative dissolution mechanism of uranium dioxide. The effect of pH and oxygen partial pressure

Author keywords

[No Author keywords available]

Indexed keywords

CARBONATES; CONCENTRATION (PROCESS); NUCLEAR FUELS; OXIDATION; PARTIAL PRESSURE; PH EFFECTS; PROTONS; RADIOLYSIS; REACTION KINETICS; SURFACES;

EID: 12844281838     PISSN: 02729172     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (27)

References (14)
  • 1
    • 0031123433 scopus 로고    scopus 로고
    • Kinetics of corrosion and dissolution of uranium dioxide as a function of pH
    • Torrero, M.E.; Baraj, E.; de Pablo, J.; Giménez, J. and Casas, I. (1997), Kinetics of corrosion and dissolution of uranium dioxide as a function of pH. Int. J. Chem. Kinet. 29, 261-267.
    • (1997) Int. J. Chem. Kinet. , vol.29 , pp. 261-267
    • Torrero, M.E.1    Baraj, E.2    De Pablo, J.3    Giménez, J.4    Casas, I.5
  • 3
    • 1542670028 scopus 로고
    • Spent fuel dissolution and oxidation. An evaluation of literature data
    • Grambow, B. (1989) Spent fuel dissolution and oxidation. An evaluation of literature data. SKB Technical Report 89-13.
    • (1989) SKB Technical Report , vol.89 , Issue.13
    • Grambow, B.1
  • 4
    • 12844274762 scopus 로고
    • Corrosion tests on spent PWR fuel in synthetic groundwater
    • Forsyth, R.S. and Werme, L.O. (1987) Corrosion tests on spent PWR fuel in synthetic groundwater. Studsvik Report 87/18.
    • (1987) Studsvik Report , vol.87 , Issue.18
    • Forsyth, R.S.1    Werme, L.O.2
  • 5
    • 0002447171 scopus 로고
    • Dissolution of irradiated fuel: A radiolytic mass balance study
    • 1995
    • Eriksen, T.E.; Eklund, U.-B.; Werme, L.O. and Bruno, J. (1995) Dissolution of irradiated fuel: a radiolytic mass balance study. J. Nucl. Mater. 227, 76-82 (1995).
    • (1995) J. Nucl. Mater. , vol.227 , pp. 76-82
    • Eriksen, T.E.1    Eklund, U.-B.2    Werme, L.O.3    Bruno, J.4
  • 9
    • 0029232176 scopus 로고
    • Uranium (IV) dioxide and SIMFUEL as a chemical analogues of nuclear spent fuel matrix dissolution
    • Bruno, J.; Casas, I.; Cera, E.; de Pablo, J.; Giménez, J. and Torrero, M.E. (1995) Uranium (IV) dioxide and SIMFUEL as a chemical analogues of nuclear spent fuel matrix dissolution. Mater. Res. Soc. Symp. Proc. 353, 601-608.
    • (1995) Mater. Res. Soc. Symp. Proc. , vol.353 , pp. 601-608
    • Bruno, J.1    Casas, I.2    Cera, E.3    De Pablo, J.4    Giménez, J.5    Torrero, M.E.6
  • 10
    • 0000209132 scopus 로고
    • Surface complexation modelling in aqueous geochemistry
    • (eds. M.F. Hochella Jr. And A.F. White), Chapter 5 The Mineralogical Society of America
    • Davis, J.A. and Kent D.B. (1990) Surface complexation modelling in aqueous geochemistry. In Review in Mineralogy: Mineral Water Interface Geochemistry (eds. M.F. Hochella Jr. And A.F. White), Vol. 23 Chapter 5, pp. 177-260. The Mineralogical Society of America.
    • (1990) Review in Mineralogy: Mineral Water Interface Geochemistry , vol.23 , pp. 177-260
    • Davis, J.A.1    Kent, D.B.2
  • 13
    • 0011378934 scopus 로고    scopus 로고
    • Uranium dioxide, SIMFUEL, and spent fuel dissolution rates. a review of published data
    • Oversby, V. (1999) Uranium dioxide, SIMFUEL, and spent fuel dissolution rates. A review of published data. SKB Technical Report TR-99-22.
    • (1999) SKB Technical Report , vol.TR-99-22
    • Oversby, V.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.