Updated safety analysis of ITER

Taylor, Neill; Baker, D.; Ciattaglia, S.; Cortes, Pierre; Elbez-Uzan, Joëlle; Iseli, Markus; Reyes, S.; Rodrı́guez-Rodrigo, L.; Rosanvallon, S.; Topilski, L.

doi:10.1016/j.fusengdes.2010.11.037

Cited by 35 publications

(18 citation statements)

References 4 publications

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“…Accurately estimating tritium retention in plasma facing components (PFCs) and minimizing its uncertainty are key safety issues for licensing DEMO and future fusion power reactors [1][2][3]. Deuterium-tritium fusion reactions produce 14 MeV neutrons that activate PFCs and create radiation defects throughout the bulk of the material of these components.…”

Section: Introductionmentioning

confidence: 99%

Defect annealing and thermal desorption of deuterium in low dose HFIR neutron-irradiated tungsten

Shimada

Hara

Otsuka

et al. 2015

Journal of Nuclear Materials

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a b s t r a c tThree tungsten samples irradiated at High Flux Isotope Reactor at Oak Ridge National Laboratory were exposed to deuterium plasma (ion fluence of 1 Â 10 26 m À2 ) at three different temperatures (100, 200, and 500°C) in Tritium Plasma Experiment at Idaho National Laboratory. Subsequently, thermal desorption spectroscopy was performed with a ramp rate of 10°C min À1 up to 900°C, and the samples were annealed at 900°C for 0.5 h. These procedures were repeated three times to uncover defect-annealing effects on deuterium retention. The results show that deuterium retention decreases approximately 70% for at 500°C after each annealing, and radiation damages were not annealed out completely even after the 3rd annealing. TMAP modeling revealed the trap concentration decreases approximately 80% after each annealing at 900°C for 0.5 h.

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Section: Introductionmentioning

confidence: 99%

Defect annealing and thermal desorption of deuterium in low dose HFIR neutron-irradiated tungsten

Shimada

Hara

Otsuka

et al. 2015

Journal of Nuclear Materials

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“…Dust in fusion devices is still an open issue from the point of view of plasma operations and safety [1,2] due to its high fuel retention capability and mobility. Investigation on dust collected in existing tokamaks [3][4][5] shows the presence of a wide range of dust size and composition depending on the nature of plasma facing components (PFCs) and on the history of tokamaks.…”

Section: Introductionmentioning

confidence: 99%

Dust characterization in FTU tokamak

Angeli

Maddaluno

Laguardia

et al. 2015

Journal of Nuclear Materials

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“…The ITER fusion device, currently under construction in the south of France, is the first nuclear fusion facility for which a full safety case has been prepared and subjected to the scrutiny of a nuclear regulator. The case was presented in the ITER safety files, in particular the preliminary safety report (Rapport Préliminaire de Sûreté, RPrS) [1,2] and examined by the French nuclear safety authorities (Autorité de Sûreté Nucléaire, ASN) and their technical advisors (Institut de Radioprotection et de Sûreté Nucléaire, IRSN) [3,4]. The safety files were also submitted to a public enquiry and assessed by the French environmental agency.…”

Section: Introductionmentioning

confidence: 99%

Lessons learnt from ITER safety & licensing for DEMO and future nuclear fusion facilities

Taylor

Cortes

2014

Fusion Engineering and Design

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One of the strong motivations for pursuing the development of fusion energy is its potentially low environmental impact and very good safety performance. But this safety and environmental potential can only be fully realized by careful design choices. For DEMO and other fusion facilities that will require nuclear licensing, S&E objectives and criteria should be set at an early stage and taken into account when choosing basic design options and throughout the design process.Studies in recent decades of the safety of fusion power plant concepts give a useful basis on which to build the S&E approach and to assess the impact of design choices. The experience of licensing ITER is of particular value, even though there are some important differences between ITER and DEMO. The ITER project has developed a safety case, produced a preliminary safety report and had it examined by the French nuclear safety authorities, leading to the licence to construct the facility. The key technical issues that arose during this process are recalled, particularly those that may also have an impact on DEMO safety. These include issues related to postulated accident scenarios, environmental releases during operation, occupational radiation exposure, and radioactive waste.

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Updated safety analysis of ITER

Cited by 35 publications

References 4 publications

Defect annealing and thermal desorption of deuterium in low dose HFIR neutron-irradiated tungsten

Defect annealing and thermal desorption of deuterium in low dose HFIR neutron-irradiated tungsten

Dust characterization in FTU tokamak

Lessons learnt from ITER safety & licensing for DEMO and future nuclear fusion facilities

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