Flow accelerated corrosion management in Indian NPPs: current practices
Description
Carbon steel piping in primary heat transport system and secondary steam circuit in a nuclear power plant is susceptible to wall thinning due to flow accelerated corrosion. Reduction of wall thickness reduces the load carrying capacity of the piping leading to leakage or rupture. In India, flow accelerated corrosion failure was observed in Kakrapar Atomic Power Station-2 (KAPS2) where a failure in secondary piping was observed. Flow accelerated corrosion has also been a major concern in feeders of PHWR plants. Internationally also catastrophic failure related to wall thinning have been observed. It becomes important to understand what techniques and tools are adopted in India for tackling the issue of flow accelerated corrosion. This paper aims to give an overview of the steps taken during design, construction and operation of NPP to tackle flow accelerated corrosion. It aims to bring out metallurgical and chemical considerations which are taken to reduce the FAC susceptibility, the inspection and surveillance programs adopted, the flow accelerated corrosion prediction models adopted for Indian NPPs. Another important element of flow accelerated corrosion management is to make a decision about dealing with the thinned component (its continuous service or replacement). All these elements of flow accelerated corrosion are presented in this paper, taking KAPS 2 secondary piping failure as a case study. (author)
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- Fourth national conference on nuclear reactor technology: emerging trends in nuclear safety
- Imprint Pagination
- 208 p.
- Journal Page Range
- [6 p.]
Conference
- Title
- 4. national conference on nuclear reactor technology
- Acronym
- NRT-4
- Dates
- 4-6 Mar 2011
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 42095245
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CARBON STEELS; CORROSION; LEAKS; PHWR TYPE REACTORS; PRIMARY COOLANT CIRCUITS; REACTOR OPERATION; RUPTURES
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; COOLING SYSTEMS; ENERGY SYSTEMS; FAILURES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRON ALLOYS; IRON BASE ALLOYS; OPERATION; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STEELS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 5 refs., 5 figs., 2 tabs.