RAMI analysis of the ITER CIS

Kitazawa, Sin‐iti; Okayama, K.; Neyatani, Y.; Sagot, F.; Houtte, D. van

doi:10.1016/j.fusengdes.2013.12.016

Cited by 13 publications

(2 citation statements)

References 3 publications

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“…However, limited instrumentation availability for liquid metal applications and aggressive operating parameters of LLCS coupled with corrosive nature of Pb-Li presents additional major challenges for process sensors and diagnostic tools. Additionally, typical interval of 2 years between scheduled maintenance cycles of ITER [4] demands precise validation and reliable performance of sensors over long duration operation. Heavy liquid metal coolants based on lead mandate the development of specially adapted and properly validated diagnostics.…”

Section: India Is Working Towards Development Of Lead Lithium Ceramicmentioning

confidence: 99%

Development of Diagnostics for High-Temperature High-Pressure Liquid Pb-16Li Applications

Saraswat¹,

Sahu²,

Rao³

et al. 2017

WJNST

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Liquid lead-lithium (Pb-16Li) is of primary interest as one of the candidate materials for tritium breeder, neutron multiplier and coolant fluid in liquid metal blanket concepts relevant to fusion power plants. For an effective and reliable operation of such high temperature liquid metal systems, monitoring and control of critical process parameters is essential. However, limited operational experience coupled with high temperature operating conditions and corrosive nature of Pb-16Li severely limited application of commercially available diagnostic tools. This paper illustrates indigenous calibration test facility designs and experimental methods used to develop non-contact configuration level diagnostics using pulse radar level sensor, wetted configuration pressure diagnostics using diaphragm seal type pressure sensor and bulk temperature diagnostics with temperature profiling for high temperature, high pressure liquid Pb and Pb-16Li applications. Calibration check of these sensors was performed using analytical methods, at temperature between 380˚C -400˚C and pressure upto 1 MPa (g). Reliability and performance validation were achieved through long duration testing of sensors in liquid Pb and liquid Pb-16Li environment for over 1000 hour. Estimated deviation for radar level sensor lies within [−3.36 mm, +13.64 mm] and the estimated error for pressure sensor lies within 1.1% of calibrated span over the entire test duration. Results obtained and critical observations from these tests are presented in this paper.

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Section: India Is Working Towards Development Of Lead Lithium Ceramicmentioning

confidence: 99%

Development of Diagnostics for High-Temperature High-Pressure Liquid Pb-16Li Applications

Saraswat¹,

Sahu²,

Rao³

et al. 2017

WJNST

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“…ITER is an international experimental nuclear fusion device with challenging technological requirements [1]. Machine protection is an important function for maintaining high reliability and safe operation in large experimental facilities such as ITER.…”

Section: Introductionmentioning

confidence: 99%

New Proposal on the Development of Machine Protection Functions for ITER Diagnostics Control

Yamamoto

Yatsuka

Hatae

et al. 2016

Plasma and Fusion Research

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There is a need to develop ITER instrumentation and control (I&C) systems with high reliabilities. Interlock systems that activate machine protection functions are implemented on robust wired-logic systems such as programmable logic controllers (PLCs). We herein propose a software tool that generates program code templates for the control systems using PLC logic. This tool decreases careless mistakes by developers and increases reliability of the program codes. A large-scale engineering database has been implemented in the ITER project. To derive useful information from this database, we propose adding semantic data to it using the Resource Description Framework format. In our novel proposal for the ITER diagnostic control system, a guide words generator that analyzes the engineering data by inference is applied to the hazard and operability study. We validated the methods proposed in this paper by applying them to the preliminary design for the I&C system of the ITER edge Thomson scattering system.

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