Failure analysis on abnormal leakage of TP321 stainless steel pipe in hydrogen-eliminated system of nuclear power plant

2018 ◽  
Vol 89 ◽  
pp. 286-292 ◽  
Author(s):  
Qun Ding ◽  
Zhen-Guo Yang ◽  
Hong-Lian Zheng ◽  
Xiao Lou
Keyword(s):  
Stainless Steel ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Failure Analysis ◽  
Nuclear Power ◽  
Steel Pipe ◽  
Stainless Steel Pipe

Research on the Stainless Steel Tubes and Pipes Material Standards of Demonstration Fast Reactor Power Plant

2013 ◽  
Author(s):  
Yaping Li ◽  
Guangdong Song
Keyword(s):  
Stainless Steel ◽  
High Temperature ◽  
Power Plant ◽  
Fast Reactor ◽  
Reactor Power ◽  
Steel Pipe ◽  
Thick Wall ◽  
Pipe Material ◽  
Stainless Steel Pipe ◽  
Reactor Power Plant

The main characteristics of the sodium pipe system in Demonstration Fast Reactor Power Plant (DFRPP) are high-temperature, thin-wall and big-caliber, which is different from high-pressure and thick-wall of the pressurized water reactor system, and the system is long-term operate in the environment of liquid metal sodium. How to guarantee the reliability of materials in high temperature are most important in material option. Engineering design depend on the criterion. Material standards are different in different countries, and corresponding construction codes are different too. Comparing the stainless steel pipe material standers at home and abroad and analyzing the material standards’ difference according to different construction codes, a stainless steel pipe material criterion system is put forward in this paper which is applicable for the DFRPP.

Risk Based Inspection Pilot Study of Ignalina Nuclear Power Plant, Unit 2

2002 ◽  
Author(s):  
Bjorn Brickstad ◽  
Adam Letzter ◽  
Arturas Klimasauskas ◽  
Robertas Alzbutas ◽  
Linas Nedzinskas ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Pilot Study ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Fracture Mechanics ◽  
Nuclear Power ◽  
Damage Mechanism ◽  
Core Damage ◽  
Steel Welds ◽  
Nuclear Power Plant Unit

A project with the acronym IRBIS (Ignalina Risk Based Inspection pilot Study) has been performed with the objective to perform a quantitative risk analysis of a total of 1240 stainless steel welds in Ignalina Nuclear Power Plant, unit 2 (INPP-2). The damage mechanism is IGSCC and the failure probabilities are quantified by using probabilistic fracture mechanics. The conditional core damage probabilities are taken from the plant PSA.

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