Concepedia

The French code RCC-M: Design and construction rules for the mechanical components of PWR nuclear islands

G. Baylac, J.M. Grandemange

Nuclear Engineering and Design · 1991 · 43 citations · 2 references

Concepts

EngineeringNuclear EngineeringNuclear MaterialsNuclear Safety AnalysisReactor PhysicsReactor Core DesignReactor DesignStructural DesignConstructionContainment Structural AnalysisContainment Thermal-mechanical BehaviorContainment Ultimate StrengthFrench Civil CodeNuclear Integrity Under Mechanical StressNuclear Reactor DesignThermal-hydraulic Code Validation

References

2

Review of fracture toughness requirements and data relevant to LWR reactor pressure vessels

David Lidbury, E. Morland · International Journal of Pressure Vessels and Piping · 1987 · 18 citations

Engineering, Materials Engineering, Nuclear Engineering +16

RCC-M (rules for design and construction of nuclear components)

Cai Heng, J.M. Grandemange, Anne-Françoise Morel · Nuclear Engineering and Design · 1987 · 10 citations

Engineering, Nuclear Engineering, Nuclear Materials +10