Obiettivo
This work programme describes 2 separate activities. Taywood Engineering Ltd (TEL) and Stangenberg, Schnellenbach and Partner (SSP) will collaborate to perform the examination and long-term assessment of nuclear power structures, and National Nuclear Corporation Ltd (NNC) will separately assess the risk of rapid stress corrosion cracking of carbon/low alloy steel and intergranular attack of stainless steel components.
The first activity (TEL/SSP) will be directed towards substantiating and redefining predictive models of the mode and pace of deterioration of nuclear power plant structures. The planned work will comprise revisiting of sites previously examined, obtaining additional experimental data and making further assessment. Furthermore, efforts will be made to include investigation at stations not previously visited within EC member countries. All results will be incorporated into a coherent data base and proposals for a planned inspection and maintenance system will be produced. There is also a need to identify means of monitoring and assessing the ongoing state of tendons and components of buildings and structures which provide protection to nuclear plant. Theoretical research will be conducted into the long-term behaviour of the prestressed concrete pressure vessel (PCPV) at THTR Schmehausen as an example. The results will be used to develop a monitoring programme for the PCPV. The planned work is a complement o contracts FI1D0030, FI1D0031 and report EUR 12758.
The second activity (NNC) will be directed towards prediction of the levels of nitric acid which will form in nuclear power plants being decommissioned and assessment of the consequences of such levels with respect to corrosion/degradation effects which could adversely influence subsequent component removal.
This work programme describes 2 separate activities. Taywood Engineering Ltd and Stangenberg, Schnellenbach and Partner collaborate to perform the examination and long term assessment of nuclear power structures, and National Nuclear Corporation Ltd separately assess the risk of rapid stress corrosion cracking of carbon/low alloy steel and intergranular attack of stainless steel components.
An inspection strategy was established and detailed plans for the inspection of reinforced concrete structures at Berkeley and Bradwell nuclear power stations have been prepared. The inspection and laboratory testing of concrete samples aims to provide the data required to assess the time taken to initiate reinforcement corrosion. Data from surveys undertaken in the preceding CEC decommissioning programme has been tabulated and detailed analysis of the data is to start shortly.
Initial investigations were undertaken into the equipment, working methods applications and capability of the impact echo and integrated optical fibre nondestructive testing techniques. These early investigations suggest that these techniques will be unable to clearly detect the presence of small flaws at the concrete steel interface in prestressed concrete structures.
The investigations dealt with the long term behaviour of prestressed concrete pressure vessels (PCPV) during the post operational state. The strain behaviour of PCPV in the post operational state was determined from data provided by the continuous safety examinations of the thorium high temperature reactor (THTR) PCPV. The comparison of calculated and measured concrete strains shows that the concrete creep was overestimated by the assumed creep law (which was defined to be independent of concrete age) and that the applicability of this creep law in connection with the law of linear superposition especially after long term release of internal pressure needs to be investigated in more detail.
Individual reactor designs have been re viewed and the state of operation established. Key items of plant have been identified for a more detailed assessment and the design of these items is being considered together with environmental factors with the object of identifying potential degradation mechanisms, such as the formation of nitric acid.
WORK PROGRAMME
1. TEL Work programme
1.1. Reinspection of Nuclear Power Plants
1.2. Extension to further Nuclear Power Plants
1.3. Compilation of Systematic Data Base
1.4. Planned Maintenance System Development
1.5. Prestressing Options Study in collaboration with SSP
1.6. Monitoring Requirements for Prestressed Concrete.
2. SSP Work programme
2.1. Development of a planned maintenance system, including long-term behaviour of materials and structured components
2.2. Study of parameters of a prestressed concrete vessel with regard to partial destressing
2.3. Monitoring requirements for a prestressed concrete pressure vessel and recommendations
3. NNC Work programme
3.1. Design review
3.2. Prediction of nitric acid concentration
3.3. Literature survey
3.4. Corrosion assessment
3.5. Environmental control
3.6. Further work.
Campo scientifico (EuroSciVoc)
CORDIS classifica i progetti con EuroSciVoc, una tassonomia multilingue dei campi scientifici, attraverso un processo semi-automatico basato su tecniche NLP. Cfr.: Il Vocabolario Scientifico Europeo.
CORDIS classifica i progetti con EuroSciVoc, una tassonomia multilingue dei campi scientifici, attraverso un processo semi-automatico basato su tecniche NLP. Cfr.: Il Vocabolario Scientifico Europeo.
- ingegneria e tecnologia altre ingegnerie e tecnologie ingegneria nucleare
- scienze sociali sociologia governance governance ambientale
- scienze naturali scienze fisiche ottica fibra ottica
- scienze sociali legge
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Coordinatore
UB1 2QX Southall
Regno Unito
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