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Additional resources for Basic Studies In The Field Of High Temperature Engineering: Third Information Exchange Meeting: Ibaraki-ken, Japan , 11-12 September 2003 (Nuclear Science)
Design codes link the materials specification and the material properties to the limiting stresses and temperatures during service for a designed lifetime, which is established via a failure criterion, and specify the applicable design rules. Safety margins are established in these design rules that incorporate the uncertainties in the materials properties data and in service conditions and the sensitivities of these data to variations in operational parameters and measurement conditions. In the US, the American Society for Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section III, Division II, Subsection CE on “Design Requirements for Graphite Core Support” was developed in the 1990s.
Welding of thick products: Process in 2004, procedure in 2005. Specifications and characterisations of large and thick forged ring: 2008. Optimisation studies: Proposal of new specification in 2006. Industrial feasibility studies of the new product selected in 2006: 2008. Mechanical studies on modified 9Cr-1Mo Creep, fatigue & relaxation properties of base metal (experiments & models) Fracture mechanics: Bending programme in 2005, tensile/torsion in 2006. Mechanical behavior of welds: Cracking 2006, residual stresses 2007.
This presentation is an independent product of the authors and does not necessarily reflect the views or regulatory position of the NRC. g. return to original volume or strength, residual strength limit, probabilistic variations in service parameters and probabilistic fracture mechanics considerations for arriving at flaw/crack size limits, which are coupled with in-service inspections. This presentation will address the challenges involved in materials specification writing that involves acceptable processing methods, establishing minimum acceptable properties and properties ranges, establishing design codes that consider appropriately the inherent variability in properties of graphite, graphite failure criteria, and the inspection requirements for nuclear graphite before use and during service.