Abstract
The paper focuses on the generic aspects of the main structural integrity issues in the liquid-sodium-cooled fast reactor. The choice of sodium as a coolant has important consequences for the deformation and failure process in the materials used for the main plant components. For example, its high boiling point means that the prim ary and secondary circuit containment operates at ambient pressure and the system loading is dominated by thermal stress. The resultant low primary stresses make leak-before-break a viable integrity criterion for all sodium boundary components. Sodium coolant operates at comparatively high temperatures and this, together with the good heat-transfer properties, means that thermal fatigue and creep are of concern, particularly in the hotter parts of the plant. A third factor concerns the steam generators, where the integrity of the sodium—water boundary is particularly important. The paper will consider the failure processes that must be addressed in relation to these conditions and the development of the integrity assessment arguments.
Reference9 articles.
1. A m erican Society of M echanical Engineers (ASME) 1986 Boiler and pressure vessel code for nuclear components Section I I I Code Case N-47.
2. Hales R. & Tom kins B. 1982 Creep fatigue failure of austenitic stainless steels relevant to structural performance. A S M E Pressure Vessel and Piping Cons. Orlando Florida. Paper 70.
3. H arrison R. P. Loosemore K . M ilne I. & Dowling A. R. containing defects. CEGB Rep. R / H / 6 Rev. 2. 1980 Assessment of the integrity of structures
4. Stable and Unstable Fatigue Crack Propagation During High Temperature Creep-Fatigue in Austenitic Steels: The Role of Precipitation
5. M unz D. (ed.) 1984 Lech-vor-Bruch Verhalten druckbeaufschlagter Komponenten. Fortschritt-Berichte der V D IZeitschriften Reihe 18 N r 14 V D I-V erlag.
Cited by
7 articles.
订阅此论文施引文献
订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献