The Experts below are selected from a list of 291 Experts worldwide ranked by ideXlab platform
F. Baqué - One of the best experts on this subject based on the ideXlab platform.
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French developments for improving In Service Inspection of SFRs
2019Co-Authors: F. Baqué, R. Raillon-picot, K. Vulliez, B. Chassignole, G. CorneloupAbstract:In Service Inspection (ISI) is a major issue to be taken into account for future Sodium Fast Reactors safety, thus, a large R&D work is performed since 2010 in France for the future SFRs. ISI requirements have been taken into account since the early pre-conceptual design phase (specific rules for design have been merged into RCC-MRx design rules until 2012), then consolidated through the basic design phase with more detailed specifications leading to increase the ISI tools ability for immersed sodium structures of SFRs, at about 200°C (shut down conditions). Inspection within the main vessel are planned with transducers immersed in sodium and also with transducers located out of sodium medium. Finally, the qualification of ISI ultrasonic transducers (for Non Destructive Examination, Telemetry and Imaging) is being performed with experimental water and sodium testing, to be compared to simulation with CIVA software platform results. A pluri-annual R&D program mainly deals with the reactor block structures, the primary components and circuit, and the Power Conversion System. Specific developments have been performed for NDE of thick austenitic steel welds, NDE using guided Lamb waves, telemetry from the outside of reactor vessel, imaging of immersed structures and components within the large primary vessel (in a pool type reactor concept) and associated in sodium robotics (with in-sodium tightness). Some results of testing and simulation are given for some ASTRID project applications.
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In Service Inspection and repair developments for SFRs
2018Co-Authors: F. Baqué, R. Marlier, Jf. Saillant, Ms. ChenaudAbstract:Within the framework of large R&D studies performed since 2010 for future sodiumcooled reactors, with a first prototype called ASTRID, in-Service Inspection and repair (ISI&R) has been identified as a major issue to be taken into account in order to improve the reactor’s safety, to consolidate its availability and to protect its related investment. Development, improvement and qualification of the ISI&R tools and processes for structures immersed in sodium at about 200°C have been performed since early pre-conceptual design phase of ASTRID This work is based on a set of consolidated specifications and a qualification process involving increasingly more realistic experiments and simulations mainly performed with the Non Destructive Examination CIVA code platform. ISI&R items (in sodium telemetry and vision, Non Destructive Examination, Laser repair, associated Robotics) are being developed and qualified as part of a multi-year program which mainly deals with the reactor block structures and primary components, and sodium circuit with the power conversion system.
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In Service Inspection and Repair of Sodium cooled ASTRID Prototype
2015Co-Authors: F. Baqué, R. Marlier, Jf. Saillant, F. Jadot, V. DelalandeAbstract:In the frame of the large R&D work which is performed for the future ASTRID sodium cooled prototype, In Service Inspection and Repair (ISI&R) has been identified as a major issue to be taken into account in order to enlarge the plant safety, to consolidate its availability and to protect the associated investment. After the first part of pre-conceptual design phase (2008-2012), the running second part of pre-conceptual phase (2013-2015) allows to increase the ISI&R tool ability for immersed sodium structures of ASTRID, at about 200°C, on the basis of consolidated specifications and thanks to their qualification through more and more realistic tests and simulation with CIVA code. ISI&R items are being developed and qualified during a pluriannual program which mainly deals with the reactor block structures, the primary components and circuit, the Power Conversion System. It ensures a strong connection between the reactor designers and Inspection specialists, as the optimization of inspectability and repairability is looked at: this already induced specific rules for design, in order to shorten and easier the ISI&R operations, which have been merged into RCC-MRx rules. Present R&D deals with the following ISI&R items: • Under sodium NDE of welding joints within the ASTRID supporting core structure (so called platelage): sodium testing and simulation are being performed. • NDE of welding joints within the ASTRID supporting core structure, from outside primary sodium (through primary vessel wall): water testing and simulation are being performed. • Under sodium NDE of welding joints within the ASTRID Above Core Structure: water testing and simulation are being performed. • Under sodium NDE of the external skirt of ASTRID Above Core Structure, • Under sodium telemetry and vision of immersed structures and components within the ASTRID primary vessel: improved techniques of scanning are studied. • Under argon coverture gas telemetry of structures and components within the ASTRID primary vessel, • NDE of the tubes of ASTRID Steam Generator Units,
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ASTRID sodium cooled fast reactor: Program for improving in Service Inspection and repair
2011 2nd International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications, 2011Co-Authors: F. Jadot, F. Baqué, Ph. J. Jeannot, G. De Dinechin, J. M. Augem, J. SibiloAbstract:In the frame of the CEA, EDF, AREVA coordinated research program for the development of Generation IV sodium-cooled fast reactors (SFR), the ASTRID project was launched in 2010. For the future prototype, the improvement of in-Service Inspection and repair (ISI&R) capabilities was identified as a major issue. Following the pluriannual SFR research program, the ISI&R main R&D axes remain: i) improvement of the primary system conceptual design, ii) development of measurement and Inspection techniques (continuous monitoring instrumentation and periodic Inspection tools), iii) accessibility and associated robotics, and iv) development and validation of repair processes. Associated ISI&R needs are being defined through an iterative method between designers and instrumentation specialists : adaptation of the Design to ISI&R requirements, fission chamber development, validation of the ultrasonic and chemical transducers, of ultrasonic non destructive simulation, of acoustic surveillance, of laser repair intervention processes, of connected robotic equipment. Moreover, CEA, as leader of the ASTRID Project, is willing to find new contributors, partners or suppliers, in order to get innovative, diversified, exhaustive and efficient solutions.
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In Service Inspection and repair of the sodium cooled ASTRID reactor prototype
2011Co-Authors: F. Baqué, R. Marlier, Jf. Saillant, F. Jadot, V. DelalandeAbstract:Within the framework of large R&D studies performed for the future sodium-cooled reactor prototype called ASTRID, in-Service Inspection and repair (ISI&R) has been identified as a major issue to be taken into account in order to improve the reactor’s safety, to consolidate its availability and to protect its related investment. Following on from the pre-conceptual design phase (2008-2012), the conceptual phase (2013-2015) is now focusing on improving the ISI&R tool for structures immersed in sodium at about 200°C in the ASTRID reactor. This work is based on a set of consolidated specifications and a qualification process involving increasingly more realistic experiments and simulations performed with the CIVA code. ISI&R items are being developed and qualified as part of a multi-year program which mainly deals with the reactor block structures, the primary components and circuit, and the power conversion system (PCS). This program is ensuring the strong ties needed between the reactor designers and Inspection specialists since the aim is to optimize inspectability and repairability. This has already induced specific rules for design in order to shorten and facilitate ISI&R operations. These new rules have been merged into the RCC-MRx rules. Current R&D deals with the following ISI&R items: • Under-sodium non-destructive examination (NDE) of welded joints on the ASTRID supporting core structure (so called strongback): sodium testing and simulation are being performed • NDE of welded joints on the ASTRID strongback supporting skirt, from outside the primary sodium (through the main vessel wall): water testing and simulation are being performed • Under-sodium NDE of welded joints on the ASTRID above-core structure: water testing and simulation are being performed • Under-sodium telemetry and vision of immersed structures and components forming the ASTRID primary vessel: improved techniques of scanning are being studied • Primary circuit cover-gas telemetry of structures and components forming the ASTRID primary vessel • Methods for in-situ repair: a laser technique has been selected • Associated in-sodium robotics: a sodium-proof material and technology is being developed and tested This paper provides the main testing and simulation results for telemetry, vision and NDE applications. R&D for Inspection and repair of SFRs faces challenging requirements and is progressing towards available technological solutions, associated with demonstrated performance levels: the basic Inspection techniques are expected to reach level 6 of ‘technological readiness’ by the end of conceptual phase. The integrated readiness level’ is also discussed in this paper with respect to access within the reactor block, fluids, positioning and maintenance aspects.
Yoshio Kamishima - One of the best experts on this subject based on the ideXlab platform.
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determination of in Service Inspection requirements for fast reactor components using system based code concept
Nuclear Engineering and Design, 2016Co-Authors: Shigeru Takaya, Yoshio Kamishima, Hideo Machida, Daigo Watanabe, Tai AsayamaAbstract:Abstract In our previous study (Takaya et al., 2015a), we proposed a new process for determining in-Service Inspection (ISI) requirements using the System Based Code concept. The proposed process consists of two complementary evaluations, one focusing on structural integrity and the other on plant safety. First, the structural reliability of a specified component is evaluated considering potentially active degradation mechanisms, including those that are not explicitly addressed in the design codes. If the structural reliability meets the requirement, the second evaluation can be conducted, which assesses the detectability of defects before they can grow to an unacceptable size, taking plant safety into account. If there is any feasible way to detect defects, it is adopted as an ISI requirement. Otherwise, a structural integrity evaluation would be required under a sufficiently conservative hypothesis. In other words, if the additional requirements are met, detectability is not an obligation. In this study, the ISI requirements for a reactor guard vessel (RGV) and core support structure (CSS) of a prototype sodium-cooled fast breeder reactor in Japan (Monju) were investigated using the proposed process. Creep-fatigue and fatigue were chosen as the potentially degradation mechanisms for the RGV and CSS, respectively. The Stage I evaluations using the Monte-Carlo method showed that both components had sufficient reliability if these degradation mechanisms were considered. At Stage II, the reliability levels of the components were evaluated assuming initial fully circumferential cracks with a depth equal to 10% of the thickness as additional requirements because there was no available Inspection method for the components. It was shown that both components had sufficient reliability even with the additional requirement based on conservative hypothesis. The failure occurrences of these components were practically eliminated. Hence, it was concluded that no ISI requirements were needed for these components. The proposed process is expected to contribute to the realization of effective and rational ISI by properly taking into account plant-specific features.
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Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements
Journal of Nuclear Engineering and Radiation Science, 2015Co-Authors: Shigeru Takaya, Yoshio Kamishima, Tai Asayama, Hideo Machida, Daigo Watanabe, Satoru Nakai, Masaki MorishitaAbstract:A new process for determination of in-Service Inspection (ISI) requirements was proposed on the basis of the system based code concept to realize effective and rational ISI by properly taking into account plant-specific features. The proposed process consists of two complementary evaluations, one focusing on structural integrity and the other one on detectability of defects before they would grow to an unacceptable size in light of plant safety. If defect detection was not feasible, structural integrity evaluation would be required under sufficiently conservative hypothesis. The applicability of the proposed process was illustrated through an application to the existing prototype fast breeder reactor, Monju.
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Study on In-Service Inspection Program and Inspection Technologies for Commercialized Sodium-Cooled Fast Reactor
Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 2006Co-Authors: Masato Ando, Shigenobu Kubo, Yoshio Kamishima, Toru IitsukaAbstract:The objective of in-Service Inspection of a nuclear power plant is to confirm integrity of function of components necessary to safety, and satisfy the needs to protect plant investment and to achieve high plant ability. The sodium-cooled fast reactor, which is designed in the feasibility study on commercialized fast reactor cycle systems in Japan, has two characteristics related to in-Service Inspection. The first is that all sodium coolant boundary structures have double-wall system. Continuous monitoring of the sodium coolant boundary structures are adopted for Inspection. The second characteristic is the steam generator with double-wall-tubes. Volumetric testing is adopted to make sure that one of the tubes can maintain the boundary function in case of the other tube failure. A rational in-Service Inspection concept was developed taking these features into account. The Inspection technologies were developed to implement in-Service Inspection plan. The under-sodium viewing system consisted of multi ultrasonic scanning transducers, which was used for imaging under-sodium structures. The under-sodium viewing system was mounted on the under-sodium vehicle and delivered to core internals. The prototype of under-sodium viewing system and vehicle were fabricated and performance tests were carried out under water. The laboratory experiments of volumetric testing for double-wall-tubes of steam generator, such as ultrasonic testing and remote-field eddy current testing, were performed and technical feasibility was assessed.Copyright © 2006 by ASME
V. Delalande - One of the best experts on this subject based on the ideXlab platform.
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In Service Inspection and Repair of Sodium cooled ASTRID Prototype
2015Co-Authors: F. Baqué, R. Marlier, Jf. Saillant, F. Jadot, V. DelalandeAbstract:In the frame of the large R&D work which is performed for the future ASTRID sodium cooled prototype, In Service Inspection and Repair (ISI&R) has been identified as a major issue to be taken into account in order to enlarge the plant safety, to consolidate its availability and to protect the associated investment. After the first part of pre-conceptual design phase (2008-2012), the running second part of pre-conceptual phase (2013-2015) allows to increase the ISI&R tool ability for immersed sodium structures of ASTRID, at about 200°C, on the basis of consolidated specifications and thanks to their qualification through more and more realistic tests and simulation with CIVA code. ISI&R items are being developed and qualified during a pluriannual program which mainly deals with the reactor block structures, the primary components and circuit, the Power Conversion System. It ensures a strong connection between the reactor designers and Inspection specialists, as the optimization of inspectability and repairability is looked at: this already induced specific rules for design, in order to shorten and easier the ISI&R operations, which have been merged into RCC-MRx rules. Present R&D deals with the following ISI&R items: • Under sodium NDE of welding joints within the ASTRID supporting core structure (so called platelage): sodium testing and simulation are being performed. • NDE of welding joints within the ASTRID supporting core structure, from outside primary sodium (through primary vessel wall): water testing and simulation are being performed. • Under sodium NDE of welding joints within the ASTRID Above Core Structure: water testing and simulation are being performed. • Under sodium NDE of the external skirt of ASTRID Above Core Structure, • Under sodium telemetry and vision of immersed structures and components within the ASTRID primary vessel: improved techniques of scanning are studied. • Under argon coverture gas telemetry of structures and components within the ASTRID primary vessel, • NDE of the tubes of ASTRID Steam Generator Units,
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In Service Inspection and repair of the sodium cooled ASTRID reactor prototype
2011Co-Authors: F. Baqué, R. Marlier, Jf. Saillant, F. Jadot, V. DelalandeAbstract:Within the framework of large R&D studies performed for the future sodium-cooled reactor prototype called ASTRID, in-Service Inspection and repair (ISI&R) has been identified as a major issue to be taken into account in order to improve the reactor’s safety, to consolidate its availability and to protect its related investment. Following on from the pre-conceptual design phase (2008-2012), the conceptual phase (2013-2015) is now focusing on improving the ISI&R tool for structures immersed in sodium at about 200°C in the ASTRID reactor. This work is based on a set of consolidated specifications and a qualification process involving increasingly more realistic experiments and simulations performed with the CIVA code. ISI&R items are being developed and qualified as part of a multi-year program which mainly deals with the reactor block structures, the primary components and circuit, and the power conversion system (PCS). This program is ensuring the strong ties needed between the reactor designers and Inspection specialists since the aim is to optimize inspectability and repairability. This has already induced specific rules for design in order to shorten and facilitate ISI&R operations. These new rules have been merged into the RCC-MRx rules. Current R&D deals with the following ISI&R items: • Under-sodium non-destructive examination (NDE) of welded joints on the ASTRID supporting core structure (so called strongback): sodium testing and simulation are being performed • NDE of welded joints on the ASTRID strongback supporting skirt, from outside the primary sodium (through the main vessel wall): water testing and simulation are being performed • Under-sodium NDE of welded joints on the ASTRID above-core structure: water testing and simulation are being performed • Under-sodium telemetry and vision of immersed structures and components forming the ASTRID primary vessel: improved techniques of scanning are being studied • Primary circuit cover-gas telemetry of structures and components forming the ASTRID primary vessel • Methods for in-situ repair: a laser technique has been selected • Associated in-sodium robotics: a sodium-proof material and technology is being developed and tested This paper provides the main testing and simulation results for telemetry, vision and NDE applications. R&D for Inspection and repair of SFRs faces challenging requirements and is progressing towards available technological solutions, associated with demonstrated performance levels: the basic Inspection techniques are expected to reach level 6 of ‘technological readiness’ by the end of conceptual phase. The integrated readiness level’ is also discussed in this paper with respect to access within the reactor block, fluids, positioning and maintenance aspects.
Tai Asayama - One of the best experts on this subject based on the ideXlab platform.
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determination of in Service Inspection requirements for fast reactor components using system based code concept
Nuclear Engineering and Design, 2016Co-Authors: Shigeru Takaya, Yoshio Kamishima, Hideo Machida, Daigo Watanabe, Tai AsayamaAbstract:Abstract In our previous study (Takaya et al., 2015a), we proposed a new process for determining in-Service Inspection (ISI) requirements using the System Based Code concept. The proposed process consists of two complementary evaluations, one focusing on structural integrity and the other on plant safety. First, the structural reliability of a specified component is evaluated considering potentially active degradation mechanisms, including those that are not explicitly addressed in the design codes. If the structural reliability meets the requirement, the second evaluation can be conducted, which assesses the detectability of defects before they can grow to an unacceptable size, taking plant safety into account. If there is any feasible way to detect defects, it is adopted as an ISI requirement. Otherwise, a structural integrity evaluation would be required under a sufficiently conservative hypothesis. In other words, if the additional requirements are met, detectability is not an obligation. In this study, the ISI requirements for a reactor guard vessel (RGV) and core support structure (CSS) of a prototype sodium-cooled fast breeder reactor in Japan (Monju) were investigated using the proposed process. Creep-fatigue and fatigue were chosen as the potentially degradation mechanisms for the RGV and CSS, respectively. The Stage I evaluations using the Monte-Carlo method showed that both components had sufficient reliability if these degradation mechanisms were considered. At Stage II, the reliability levels of the components were evaluated assuming initial fully circumferential cracks with a depth equal to 10% of the thickness as additional requirements because there was no available Inspection method for the components. It was shown that both components had sufficient reliability even with the additional requirement based on conservative hypothesis. The failure occurrences of these components were practically eliminated. Hence, it was concluded that no ISI requirements were needed for these components. The proposed process is expected to contribute to the realization of effective and rational ISI by properly taking into account plant-specific features.
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Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements
Journal of Nuclear Engineering and Radiation Science, 2015Co-Authors: Shigeru Takaya, Yoshio Kamishima, Tai Asayama, Hideo Machida, Daigo Watanabe, Satoru Nakai, Masaki MorishitaAbstract:A new process for determination of in-Service Inspection (ISI) requirements was proposed on the basis of the system based code concept to realize effective and rational ISI by properly taking into account plant-specific features. The proposed process consists of two complementary evaluations, one focusing on structural integrity and the other one on detectability of defects before they would grow to an unacceptable size in light of plant safety. If defect detection was not feasible, structural integrity evaluation would be required under sufficiently conservative hypothesis. The applicability of the proposed process was illustrated through an application to the existing prototype fast breeder reactor, Monju.
F. Jadot - One of the best experts on this subject based on the ideXlab platform.
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In Service Inspection and Repair of Sodium cooled ASTRID Prototype
2015Co-Authors: F. Baqué, R. Marlier, Jf. Saillant, F. Jadot, V. DelalandeAbstract:In the frame of the large R&D work which is performed for the future ASTRID sodium cooled prototype, In Service Inspection and Repair (ISI&R) has been identified as a major issue to be taken into account in order to enlarge the plant safety, to consolidate its availability and to protect the associated investment. After the first part of pre-conceptual design phase (2008-2012), the running second part of pre-conceptual phase (2013-2015) allows to increase the ISI&R tool ability for immersed sodium structures of ASTRID, at about 200°C, on the basis of consolidated specifications and thanks to their qualification through more and more realistic tests and simulation with CIVA code. ISI&R items are being developed and qualified during a pluriannual program which mainly deals with the reactor block structures, the primary components and circuit, the Power Conversion System. It ensures a strong connection between the reactor designers and Inspection specialists, as the optimization of inspectability and repairability is looked at: this already induced specific rules for design, in order to shorten and easier the ISI&R operations, which have been merged into RCC-MRx rules. Present R&D deals with the following ISI&R items: • Under sodium NDE of welding joints within the ASTRID supporting core structure (so called platelage): sodium testing and simulation are being performed. • NDE of welding joints within the ASTRID supporting core structure, from outside primary sodium (through primary vessel wall): water testing and simulation are being performed. • Under sodium NDE of welding joints within the ASTRID Above Core Structure: water testing and simulation are being performed. • Under sodium NDE of the external skirt of ASTRID Above Core Structure, • Under sodium telemetry and vision of immersed structures and components within the ASTRID primary vessel: improved techniques of scanning are studied. • Under argon coverture gas telemetry of structures and components within the ASTRID primary vessel, • NDE of the tubes of ASTRID Steam Generator Units,
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ASTRID sodium cooled fast reactor: Program for improving in Service Inspection and repair
2011 2nd International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications, 2011Co-Authors: F. Jadot, F. Baqué, Ph. J. Jeannot, G. De Dinechin, J. M. Augem, J. SibiloAbstract:In the frame of the CEA, EDF, AREVA coordinated research program for the development of Generation IV sodium-cooled fast reactors (SFR), the ASTRID project was launched in 2010. For the future prototype, the improvement of in-Service Inspection and repair (ISI&R) capabilities was identified as a major issue. Following the pluriannual SFR research program, the ISI&R main R&D axes remain: i) improvement of the primary system conceptual design, ii) development of measurement and Inspection techniques (continuous monitoring instrumentation and periodic Inspection tools), iii) accessibility and associated robotics, and iv) development and validation of repair processes. Associated ISI&R needs are being defined through an iterative method between designers and instrumentation specialists : adaptation of the Design to ISI&R requirements, fission chamber development, validation of the ultrasonic and chemical transducers, of ultrasonic non destructive simulation, of acoustic surveillance, of laser repair intervention processes, of connected robotic equipment. Moreover, CEA, as leader of the ASTRID Project, is willing to find new contributors, partners or suppliers, in order to get innovative, diversified, exhaustive and efficient solutions.
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In Service Inspection and repair of the sodium cooled ASTRID reactor prototype
2011Co-Authors: F. Baqué, R. Marlier, Jf. Saillant, F. Jadot, V. DelalandeAbstract:Within the framework of large R&D studies performed for the future sodium-cooled reactor prototype called ASTRID, in-Service Inspection and repair (ISI&R) has been identified as a major issue to be taken into account in order to improve the reactor’s safety, to consolidate its availability and to protect its related investment. Following on from the pre-conceptual design phase (2008-2012), the conceptual phase (2013-2015) is now focusing on improving the ISI&R tool for structures immersed in sodium at about 200°C in the ASTRID reactor. This work is based on a set of consolidated specifications and a qualification process involving increasingly more realistic experiments and simulations performed with the CIVA code. ISI&R items are being developed and qualified as part of a multi-year program which mainly deals with the reactor block structures, the primary components and circuit, and the power conversion system (PCS). This program is ensuring the strong ties needed between the reactor designers and Inspection specialists since the aim is to optimize inspectability and repairability. This has already induced specific rules for design in order to shorten and facilitate ISI&R operations. These new rules have been merged into the RCC-MRx rules. Current R&D deals with the following ISI&R items: • Under-sodium non-destructive examination (NDE) of welded joints on the ASTRID supporting core structure (so called strongback): sodium testing and simulation are being performed • NDE of welded joints on the ASTRID strongback supporting skirt, from outside the primary sodium (through the main vessel wall): water testing and simulation are being performed • Under-sodium NDE of welded joints on the ASTRID above-core structure: water testing and simulation are being performed • Under-sodium telemetry and vision of immersed structures and components forming the ASTRID primary vessel: improved techniques of scanning are being studied • Primary circuit cover-gas telemetry of structures and components forming the ASTRID primary vessel • Methods for in-situ repair: a laser technique has been selected • Associated in-sodium robotics: a sodium-proof material and technology is being developed and tested This paper provides the main testing and simulation results for telemetry, vision and NDE applications. R&D for Inspection and repair of SFRs faces challenging requirements and is progressing towards available technological solutions, associated with demonstrated performance levels: the basic Inspection techniques are expected to reach level 6 of ‘technological readiness’ by the end of conceptual phase. The integrated readiness level’ is also discussed in this paper with respect to access within the reactor block, fluids, positioning and maintenance aspects.
