Graham B. Heys
Health and Safety Executive
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Publication
Featured researches published by Graham B. Heys.
Journal of Pressure Vessel Technology-transactions of The Asme | 2003
Ernest D. Eason; Edward E. Nelson; Graham B. Heys
Models of fatigue crack growth rates for medium and low sulfur ferritic pressure vessel steels in pressurized water reactor (PWR) primary environments are developed based on a recent collection of UK data and the EPRI Database for Environmentally Assisted Cracking (EDEAC). The combined UK and EDEAC database contains a broader range of experimental conditions specific to PWRs than either database by itself Both probabilistic and conventional crack growth rate models are developed that reduce unnecessary conservatism for medium and low sulfur PWR primary water applications and eliminate the explicit dependence on rise time that caused difficulties applying prior models.
ASME 2003 Pressure Vessels and Piping Conference | 2003
Ernest D. Eason; Edward E. Nelson; Graham B. Heys
Models of fatigue crack growth rates for medium and low sulfur ferritic pressure vessel steels in pressurized water reactor (PWR) primary environments are developed based on a recent collection of UK data and the EPRI Database for Environmentally Assisted Cracking (EDEAC). The combined UK and EDEAC database contains a broader range of experimental conditions specific to PWRs than either database by itself. Both probabilistic and conventional crack growth rate models are developed that reduce unnecessary conservatism for medium and low sulfur PWR primary water applications and eliminate the explicit dependence on rise time that caused difficulties applying prior models.Copyright
Journal of Nuclear Materials | 2013
Ernest D. Eason; Graham Hall; Barry Marsden; Graham B. Heys
Journal of Nuclear Materials | 2013
Ernest D. Eason; Graham Hall; Barry Marsden; Graham B. Heys
Journal of Nuclear Materials | 2013
Ernest D. Eason; Graham Hall; Barry Marsden; Graham B. Heys
Journal of Nuclear Materials | 2008
Ernest D. Eason; Graham Hall; Barry Marsden; Graham B. Heys
Journal of Nuclear Materials | 2008
Ernest D. Eason; Graham Hall; Graham B. Heys; J.F. Knott; Barry Marsden; S D Preston; T Swan
In: Securing the Safe Performance of Graphite Reactor Cores, Nottingham: Securing the Safe Performance of Graphite Reactor Cores, Nottingham; 2008. | 2008
K. McNally; E. Tan; N. Warren; Graham B. Heys; Barry Marsden
In: 2011 Simulia Customer Conference: Simulia Customer Conference; 17 May 2011-19 May 2011; Barcelona. 2011. p. 570-581. | 2011
D.K.L. Tsang; Barry Marsden; Graham B. Heys
Unknown Journal | 2010
D.K.L. Tsang; Barry Marsden; Graham B. Heys