1970
DOI: 10.1016/0029-5493(70)90096-8
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Viscoelastic response of graphitic materials in irradiation environments

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1972
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Cited by 9 publications
(3 citation statements)
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“…Consequently, specially written coding is required to model the behaviour of irradiated graphite components. A viscoelastic graphite model was first produced in the USA by Chang and Rashid [4]. Later, a model called VIENUS was created by JAERI in Japan for a HTTR graphite block by Iyoku et al [5].…”
Section: Introductionmentioning
confidence: 99%
“…Consequently, specially written coding is required to model the behaviour of irradiated graphite components. A viscoelastic graphite model was first produced in the USA by Chang and Rashid [4]. Later, a model called VIENUS was created by JAERI in Japan for a HTTR graphite block by Iyoku et al [5].…”
Section: Introductionmentioning
confidence: 99%
“…Relief of these stresses through radiationinduced creep is, thus, an important factor i n HTGR design. (95)(96)(97) Thermally induced creep of graphite does not occur a t significant r a t e s below about 2000°C, but radiation-induced creep occurs a t significant r a t e s a t a l l temperatures investigated. Creep takes place i n two stages; the f i r s t (or primary creep) stage, which i s approximately a logrithmic function of fluence and approximately proportional t o the i n i t i a l e l a s t i c s t r a i n , is a reversable process and rapidly goes t o completion a t low fluences.…”
Section: Radiation C R E E~mentioning
confidence: 99%
“…Hence, the finite element method (FEM) is widely used in graphite stress analysis and lifetime assessments. The innovative FEM code for stress analysis of nuclear graphite components, which was first openly reported in 1970, was developed by Chang [34]. Posterior research conducted by Smith [35] introduced a FEM methodology and software designed for stress analysis of high temperature reactor graphite components.…”
Section: Introductionmentioning
confidence: 99%