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Volumn 346, Issue 1, 2005, Pages 5-15

The effects of alpha-radiolysis on UO2 dissolution determined from batch experiments with 238Pu-doped UO2

Author keywords

[No Author keywords available]

Indexed keywords

DISSOLUTION; DOPING (ADDITIVES); HYDROGEN PEROXIDE; PLUTONIUM; RADIOISOTOPES; URANIUM DIOXIDE;

EID: 26444538482     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2005.04.069     Document Type: Conference Paper
Times cited : (15)

References (26)
  • 1
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    • Fuel corrosion processes under waste disposal conditions
    • AECL-12034
    • D.W. Shoesmith, Fuel corrosion processes under waste disposal conditions. Atomic Energy of Canada Limited Report, AECL-12034, 1999.
    • (1999) Atomic Energy of Canada Limited Report
    • Shoesmith, D.W.1
  • 10
    • 0142017372 scopus 로고    scopus 로고
    • A mixed-potential model for the prediction of the effects of alpha-radiolysis, precipitation and redox processes on the dissolution of used nuclear fuel
    • Ontario Hydro
    • D.W. Shoesmith, F. King, A mixed-potential model for the prediction of the effects of alpha-radiolysis, precipitation and redox processes on the dissolution of used nuclear fuel. Ontario Hydro, Nuclear Waste Management Division Report 06819-REP-01200-0038-R00, 1998.
    • (1998) Nuclear Waste Management Division Report 06819-REP-01200-0038-R00
    • Shoesmith, D.W.1    King, F.2
  • 11
    • 0009852748 scopus 로고    scopus 로고
    • The disposal of Canada's nuclear fuel waste: A study of postclosure safety of in-room emplacement of used CANDU fuel in copper containers in permeable plutonic rock, vol. 2: Vault model
    • AECL-11494-2, COG-96-552-2
    • L.H. Johnson, D.M. LeNeveu, F. King, D.W. Shoesmith, M. Kolar, D.W. Oscarson, S.Sunder, C. Onofrei, J.L. Crosthwaite, The disposal of Canada's nuclear fuel waste: A study of postclosure safety of in-room emplacement of used CANDU fuel in copper containers in permeable plutonic rock, vol. 2: vault model. Atomic Energy of Canada Limited Report, AECL-11494-2, COG-96-552-2, 1996.
    • (1996) Atomic Energy of Canada Limited Report
    • Johnson, L.H.1    Leneveu, D.M.2    King, F.3    Shoesmith, D.W.4    Kolar, M.5    Oscarson, D.W.6    Sunder, S.7    Onofrei, C.8    Crosthwaite, J.L.9
  • 12
    • 0142081102 scopus 로고    scopus 로고
    • 2 using the mixed-potential model of fuel dissolution (MPM version 1.1)
    • Ontario Power Generation Toronto, Ontario
    • 2 using the mixed-potential model of fuel dissolution (MPM version 1.1). Ontario Power Generation, Nuclear Waste Management Division Report 06819-REP-01200-10014, 1999. Toronto, Ontario.
    • (1999) Nuclear Waste Management Division Report 06819-REP-01200-10014
    • King, F.1    Kolar, M.2
  • 13
    • 26444490115 scopus 로고    scopus 로고
    • Analysis of the effect of cladding on the oxidative dissolution of used nuclear fuel using the mixed potential model of fuel dissolution (MPM Version 1.2)
    • Ontario Power Generation Toronto, Ontario
    • F. King, M. Kolar, Analysis of the effect of cladding on the oxidative dissolution of used nuclear fuel using the mixed potential model of fuel dissolution (MPM Version 1.2). Ontario Power Generation, Nuclear Waste Management Division Report 06819-REP-01200-10022, 2000. Toronto, Ontario.
    • (2000) Nuclear Waste Management Division Report 06819-REP-01200-10022
    • King, F.1    Kolar, M.2
  • 14
    • 26444543374 scopus 로고    scopus 로고
    • Mixed potential model simulations of the effects of porous film formation on the dissolution of used fuel (MPM Version 1.3)
    • Ontario Power Generation Toronto, Ontario
    • F. King, M. Kolar, Mixed potential model simulations of the effects of porous film formation on the dissolution of used fuel (MPM Version 1.3). Ontario Power Generation, Nuclear Waste Management Division Report 06819-REP-01300- 10019-R00, 2001a. Toronto, Ontario.
    • (2001) Nuclear Waste Management Division Report 06819-REP-01300-10019-R00
    • King, F.1    Kolar, M.2
  • 15
    • 26444609178 scopus 로고    scopus 로고
    • An improved C-steel corrosion model for the mixed-potential model for used fuel dissolution (MPM Version 1.4)
    • Ontario Power Generation Toronto, Ontario
    • F. King, M. Kolar, An improved C-steel corrosion model for the mixed-potential model for used fuel dissolution (MPM Version 1.4). Ontario Power Generation, Nuclear Waste Management Division Report 06819-REP-01300-10027-R00, 2001b. Toronto, Ontario.
    • (2001) Nuclear Waste Management Division Report 06819-REP-01300-10027-R00
    • King, F.1    Kolar, M.2
  • 16
    • 26444614231 scopus 로고    scopus 로고
    • Validation of the mixed-potential model for used fuel dissolution against experimental data
    • Ontario Power Generation Toronto, Ontario
    • F. King, M. Kolar, Validation of the mixed-potential model for used fuel dissolution against experimental data. Ontario Power Generation, Nuclear Waste Management Division Report 06819-REP-01200-10077-R00, 2002a. Toronto, Ontario.
    • (2002) Nuclear Waste Management Division Report 06819-REP-01200-10077-R00
    • King, F.1    Kolar, M.2
  • 23
    • 26444468190 scopus 로고    scopus 로고
    • The interaction of radiolysis products and canister corrosion products and the implications for spent fuel dissolution and radionuclide transport in a repository for spent fuel
    • Switzerland
    • L.H. Johnson, P.A. Smith, The interaction of radiolysis products and canister corrosion products and the implications for spent fuel dissolution and radionuclide transport in a repository for spent fuel. NAGRA Technical Report NTB 00-04, Switzerland, 2000.
    • (2000) NAGRA Technical Report , vol.NTB 00-04
    • Johnson, L.H.1    Smith, P.A.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.