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Publisher: Elsevier

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Volume 79, Number 8, August 2002

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Online access for everyone via ScienceDirect
pp. v-vi(2)
Author: Eastbury, D.

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Use of damage monitoring systems for component life optimisation in power plant
pp. 541-547(7)
Authors: Paterson, I.R.; Wilson, J.D.

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Sizing of cracks using the alternating current field measurement technique
pp. 549-554(6)
Authors: LeTessier, R.; Coade, R.W.; Geneve, B.

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The economics of repeated tube thickness surveys
pp. 555-559(5)
Author: Price, J.

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The potential for using high chromium ferritic alloys for hydroprocessing reactors
pp. 561-569(9)
Authors: Antalffy, L.P.; Chaku, P.N.; Canonico, D.A.; Pfeifer, J.A.; Alcorn, D.G.

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Microstructure and microchemistry variation during thermal exposure of low alloy steels
pp. 571-576(6)
Authors: Kim, S.; Shekhter, A.; Ringer, S.P.

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Irradiation effects in reactor pressure vessel steels
pp. 617-618(2)
Authors: Davies, M.; Bolton, C.; English, C.; Nicholson, R.; Priest, B.; Williams, T.

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Radiation embrittlement of low-alloy steels
pp. 619-636(18)
Authors: Nikolaev, Y.A.; Nikolaeva, A.V.; Shtrombakh, Y.I.

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Irradiation embrittlement of model alloys and commercial steels: analysis of similitude behaviors
pp. 637-642(6)
Authors: Debarberis, L.; Sevini, F.; Acosta, B.; Kryukov, A.; Nikolaev, Y.; Amaev, A.D.; Valo, M.

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Radiation embrittlement kinetics of the first generation of VVER-440 RVPs after post-irradiation annealing
pp. 643-648(6)
Authors: Platonov, P.A.; Nikolaev, Y.A.; Shtrombakh, Y.I.

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A model of irradiation damage in high nickel submerged arc welds
pp. 649-660(12)
Authors: Williams, T.J.; Ellis, D.; English, C.A.; Hyde, J.

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Extended analysis of VVER-1000 surveillance data
pp. 661-664(4)
Authors: Kryukov, A.; Erak, D.; Debarberis, L.; Sevini, F.; Acosta, B.

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SCK.CEN contribution to the IAEA Round Robin exercise on WWER-440 RPV weld material: irradiation, annealing and re-embrittlement
pp. 665-684(20)
Authors: Lucon, E.; van Walle, E.; Scibetta, M.; Chaouadi, R.; Willekens, M.; Weber, M.

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Fracture toughness of weld metal samples removed from a decommissioned Magnox reactor pressure vessel
pp. 685-692(8)
Authors: Bolton, C.J.; Bischler, P.J.E.; Wootton, M.R.; Moskovic, R.; Morri, J.R.; Pegg, H.C.; Haines, A.B.; Smith, R.F.; Woodman, R.

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Application of Master Curve fracture toughness for reactor pressure vessel integrity assessment in the USA
pp. 701-713(13)
Authors: Server, W.; Rosinski, S.; Lott, R.; Kim, C.; Weakland, D.

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