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Volumn , Issue , 2004, Pages 761-769

Modelling of defect structure evolution in irradiated UO2 fuel in the MFPR code

Author keywords

[No Author keywords available]

Indexed keywords

BUBBLES (IN FLUIDS); DISLOCATIONS (CRYSTALS); FISSION REACTIONS; POINT DEFECTS; URANIUM DIOXIDE;

EID: 32044434917     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (3)

References (27)
  • 1
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    • (1994) NUREG/CR-5840 TI92 040783
    • Rest, J.1    Zawadzki, S.A.2
  • 2
    • 0003737834 scopus 로고
    • Victoria, a mechanistic model of radionuclide behavior in the reactor coolant system under normal and severe accident conditions
    • T.J. HEAMES, et al "VICTORIA, a Mechanistic Model of Radionuclide Behavior in the Reactor Coolant System under Normal and Severe Accident conditions," NUREG/CR-5545 SAND90-0756 Rev1 R3, R4, (1992)
    • (1992) NUREG/CR-5545 SAND90-0756 Rev1 R3, R4
    • Heames, T.J.1
  • 4
    • 0027693960 scopus 로고
    • Formation and growth of intragranular bubbles in UC>2 fuels with burn-up of 6-83 Gwd/t
    • S. KASHIBE, K. UNE and K. NOGITA, "Formation and Growth of Intragranular Bubbles in UC>2 Fuels with Burn-up of 6-83 Gwd/t," Journal of Nuclear Materials, 206, 22 (1993).
    • (1993) Journal of Nuclear Materials , vol.206 , pp. 22
    • Kashibe, S.1    Une, K.2    Nogita, K.3
  • 9
    • 84950654481 scopus 로고
    • Fission gas release during post irradiation annealing of BWR fuel
    • K. UNE and S. KASHIBE, "Fission Gas Release during Post Irradiation Annealing of BWR Fuel," Journal of Nuclear Science and technology, 27(11), 1002 (1990).
    • (1990) Journal of Nuclear Science and Technology , vol.27 , Issue.11 , pp. 1002
    • Une, K.1    Kashibe, S.2
  • 10
    • 0032094810 scopus 로고    scopus 로고
    • Thermal treatment of uranium oxide irradiated in pressurized water reactor: Swelling and release of fission gases
    • I. ZACHARIE et al, "Thermal Treatment of Uranium Oxide Irradiated in Pressurized Water Reactor: Swelling and Release of Fission Gases," Journal of Nuclear Materials, 255, 85 (1998).
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    • Zacharie, I.1
  • 13
    • 0002767286 scopus 로고
    • Cascade damage effects on the swelling of irradiated materials
    • R. BULLOUGH, B.L. EYREE and K. KRISHAN, "Cascade Damage Effects on the Swelling of Irradiated Materials," Proc.R.Soc.Lond, A346, 81 (1975).
    • (1975) Proc. R. Soc. Lond , vol.A346 , pp. 81
    • Bullough, R.1    Eyree, B.L.2    Krishan, K.3
  • 16
    • 0022926339 scopus 로고
    • Diffusion in ceramic oxide systems
    • H. MATZKE, "Diffusion in ceramic Oxide Systems," Adv.Ceram, 17, 1 (1986).
    • (1986) Adv. Ceram , vol.17 , pp. 1
    • Matzke, H.1
  • 19
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    • The nucleation and early growth of interstitial dislocation loops in irradiated materials
    • M.R. HAYNS, "The Nucleation and Early Growth of Interstitial Dislocation Loops in Irradiated Materials," Journal of Nuclear Materials, 56, 267 (1975).
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    • An alternative explanation for evidence that Xe depletion, pore formation and grain subdivision begin at different local burnups
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    • Rest, J.1
  • 21
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    • Dislocation loop growth and void swelling in bounded media by charged particle damage
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    • Yoo, M.H.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.