Development of a Young’s modulus model for Gilsocarbon graphites irradiated in inert environments

Eason, E.D.; Hall, Graham; Marsden, Barry; Heys, Graham B.

doi:10.1016/j.jnucmat.2008.07.036

Cited by 9 publications

(4 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…This is the case with Gilsocarbon and other nuclear graphite grades in which initially there is a small increase in volume between zero fluence and about ∼10 × 10 20 n cm −2 EDND, 5 see Fig. 3.…”

Section: Empirical Materials Test Reactor Datamentioning

confidence: 82%

“…Dimensional changes at low temperature (below ∼650°C ) in semi-isotropic graphite sometimes exhibit a low fluence delay in shrinkage and even some swelling. This is the case with Gilsocarbon and other nuclear graphite grades in which initially there is a small increase in volume between zero fluence and about ∼10 × 10 20 n cm −2 EDND, 5 see Fig. 3.…”

Section: Empirical Materials Test Reactor Datamentioning

confidence: 82%

See 1 more Smart Citation

Dimensional change, irradiation creep and thermal/mechanical property changes in nuclear graphite

Marsden

Haverty

Bodel

et al. 2016

International Materials Reviews

109

View full text Add to dashboard Cite

Since the start of the 'nuclear age' graphite has been employed as a moderator in around 100 nuclear reactors, and today there are still some 30 graphite-moderated reactors operating and there are plans for new Generation IV high-temperature reactors. Many of the graphite moderator reactors now producing power are operating beyond their original design life. Therefore in some cases, to aid the reactor operators and designers, the existing graphite irradiation databases need to be extended either to a higher temperature or higher neutron fluence. Furthermore, data are needed for the different grades of graphite that are available at present. This can either be achieved by expensive, time consuming irradiation programmes or by improving the understanding of the mechanisms and processes which lead to irradiationinduced dimensional and property changes in the graphite core components. This review looks at three of the most important graphite properties which change with exposure to irradiation, namely dimensional change, irradiation creep and thermal expansion. The behaviour of UK AGR, Magnox and an experimental grade of German reactor graphite are explored in some detail. First graphite reactor core design is briefly discussed, giving examples of typical graphite components and core arrangements. Issues related to aging graphite component and core behaviour are illustrated through examples of component internal and thermal stress generation, and issues related to whole core behaviour are also outlined. Second the manufacture and microstructure of different nuclear graphite grades are discussed, highlighting how the choice of raw materials and manufacturing technique influences the graphite properties. Third the coefficient of thermal expansion, dimensional change and irradiation creep are analysed using microstructural and averaging methods which are used to relate crystal to bulk properties by accounting for graphite crystal orientation and porosity. These techniques, which were first applied to nuclear graphite in the 1960s, are extended and discussed with the aim of trying to lend some understanding to the role the microstructural crystallite and porosity distributions play in defining the dimensional stability and properties of virgin graphite, irradiated graphite and stressed graphite.

show abstract

Section: Empirical Materials Test Reactor Datamentioning

confidence: 82%

Section: Empirical Materials Test Reactor Datamentioning

confidence: 82%

Dimensional change, irradiation creep and thermal/mechanical property changes in nuclear graphite

Marsden

Haverty

Bodel

et al. 2016

International Materials Reviews

109

View full text Add to dashboard Cite

show abstract

“…Fig. 3 shows the dimensional change behaviour; the curves added for guidance are based on a statistical analysis by Eason et al [4] for various grades of Gilsocarbon graphite irradiated at temperatures between $300 and $650°C. Although the use of this empirical fit to this higher temperature data is not ideal, the fits indicate that the samples reported here are approaching dimensional change 'turn-around'.…”

Section: Gilsocarbon Irradiation Resultsmentioning

confidence: 99%

Dimensional and material property changes to irradiated Gilsocarbon graphite irradiated between 650 and 750°C

Marsden

Hall

Wouters

et al. 2008

Journal of Nuclear Materials

Self Cite

View full text Add to dashboard Cite

“…Two irradiation effects models have been completed and undergone a residual analysis to date; a dimensional change model of Gilsocarbon irradiated in an inert atmosphere in the approximate temperature range 300-650°C [17], and a Young's modulus ratio model (irradiated modulus divided by unirradiated modulus or E/ E 0 ) of Gilsocarbon irradiated in an inert atmosphere in that same temperature range [19]. In the dimensional change case (Fig.…”

Section: Statistical Evaluation Of Uk Graphite Datamentioning

confidence: 99%

The origins and use of the equivalent temperature concept

Eason¹,

Hall

Heys

et al. 2008

Journal of Nuclear Materials

View full text Add to dashboard Cite

Development of a Young’s modulus model for Gilsocarbon graphites irradiated in inert environments

Cited by 9 publications

References 3 publications

Dimensional change, irradiation creep and thermal/mechanical property changes in nuclear graphite

Dimensional change, irradiation creep and thermal/mechanical property changes in nuclear graphite

Dimensional and material property changes to irradiated Gilsocarbon graphite irradiated between 650 and 750°C

The origins and use of the equivalent temperature concept

Contact Info

Product

Resources

About