Shoesmith, David William.
Shoesmith, David William, 19..-....
Shoesmith, D. W.
VIAF ID: 21402629 ( Personal )
Permalink: http://viaf.org/viaf/21402629
Preferred Forms
- 100 1 _ ‡a Shoesmith, D. W.
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- 100 1 _ ‡a Shoesmith, David William, ‡d 19..-....
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4xx's: Alternate Name Forms (3)
Works
Title | Sources |
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Anodic dissolution of UO₂ in slightly alkaline sodium perchlorate solutions | |
An assessment of the feasibility of indefinite containment of Canadian nuclear fuel wastes | |
The behaviour of radium in soil and in uranium mine-tailings | |
The cathodic reduction of dioxygen on uranium oxide in dilute alkaline aqueous solution | |
Chemistry of UO₂ fuel dissolution in relation to the disposal of used nuclear fuel | |
Comportement du radium dans le sol et dans les résidus de mines d'uranium | |
Corrosion of nuclear fuel waste containers : proceedings of a workshop held in Winnipeg, Manitoba, 1988 February 9-10 | |
(D.W. Shoesmith) | |
Development of a kinetic model to predict the rate of oxidation and dissolution of nuclear fuel (UO₂) by the radiolysis of water | |
The effects of gamma radiation on the corrosion of candidate materials for the fabrication of nuclear waste packages | |
Electrochemical techniques in corrosion science and engineering, c2003: | |
Évaluation de la faisabilité du confinement illimité des déchets de combustible nucléaire canadiens | |
Facteurs influant sur la réactivité et la vitesse de corrosion de l'UO₂ et du combustible irradié | |
Factors affecting the differences in reactivity and dissolution rates between UO₂ and spent nuclear fuel | |
Formation, transformation and dissolution of phases formed on surfaces | |
Hydrogen absorption and the lifetime performance of titanium nuclear waste containers | |
Mise au point d'un modl̈e cinťique pour prďire la vitesse d'oxydation et de dissolution du combustible nuclǎire (UOŒ2) par radiolyse de l'eau | |
Modèle basé sur l'électrochimie pour la dissolution de l'UO@ | |
Modèle de calcul de la durée de vie des conteneurs en titane nuance 2 pour déchets nucléaires | |
Modelling the effects of porous and semi-permeable layers on corrosion processes | |
Prediction of long-term behaviour for nuclear waste disposal | |
Proceedings of CORROSION/2003 research topical symposium | |
Processus de corrosion du combustible dans les conditions de stockage permanent des déchets | |
Résistance du titane à la corrosion par piqûres, à la corrosion d'origine microbienne et à la corrosion dans des conditions non saturées | |
The resistence of titanium to pitting, microbially induced corrosion and corrosion in unsaturated conditions | |
Review of the expected behaviour of alpha titanium alloys under Yucca Mountain conditions = Examen du comportement prévu des alliages de titane alpha dans les conditions du mont Yucca | |
Scientific basis for nuclear waste management XXIII, c2000: | |
Validation of the oxidative dissolution model for used CANDU fuel |