Code development and characteristics analysis for Leak Before Break in the pipelines of Sodium-cooled Fast Reactor

Author:

Wu DiORCID,Gui Minyang,Zhang Jing,Wu YingweiORCID,Wang ChenglongORCID,Wang Mingjun,Su G.H.

Funder

National Postdoctoral Program for Innovative Talents

China Postdoctoral Science Foundation

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference33 articles.

1. Identification of fluid flow regimes in narrow cracks;Bagshaw;Proc. Inst. Mech. Eng. Part C: J. Mech. Eng. Sci.,2000

2. Explicit equations for leak rates through narrow cracks;Beck;Int. J. Press. Vessels Pip.,2005

3. Bhandari, S., Deschanels, H., Spérandio, M., Faidy, C., Setz, A. W., 1993. Tests on large scale LMFBR piping, Part II: Analysis of through-cracked straight pipes DN700 tested under bending at RT and 550°C, SMIRT 12 Conference, Stuttgart (15-20. Aug) paper GF10/2.

4. Leak-before-break analysis of Prototype Fast Breeder Reactor main vessel;Biswas;Trans. Indian Inst. Met.,2010

5. Measurement of fluid flow rates through cracks;Clarke;Int. J. Press. Vessels Pip.,1997

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