Overview of recent ITER TBM Program activities

Giancarli, L.; Bravo, X.; Cho, Seungyon; Ferrari, Marco; Hayashi, T.; Kim, Byoung Yoon; Leal-Pereira, Artur; Martins, Jean-Pierre; Merola, M.; Romain, P.; Schneiderova, Iva; Sheng, Qian; Sircar, Amit; Strebkov, Yuri; Laan, J. van der; Ying, Alice

doi:10.1016/j.fusengdes.2020.111674

Cited by 66 publications

(23 citation statements)

References 27 publications

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“…The selection process for the four designs that will be part of the initial ITER configuration is currently underway, with one possible option involving two water-cooled TBS and two helium-cooled TBS, although these will not start operating until the last non-nuclear phase of ITER [ 59 ]. All TBM designs proposed for testing in ITER use RAFM as the structural material for the reasons below: It ensures that the BB produces very limited volumes of high-level radioactive waste, thereby seeking public acceptance of nuclear fusion.…”

Section: Structural Materialsmentioning

confidence: 99%

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Alba¹,

Rodríguez²,

Cerdeira³

2022

Materials

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This paper presents the roadmap of the main materials to be used for ITER and DEMO class reactors as well as an overview of the most relevant innovations that have been made in recent years. The main idea in the EUROfusion development program for the FW (first wall) is the use of low-activation materials. Thus far, several candidates have been proposed: RAFM and ODS steels, SiC/SiC ceramic composites and vanadium alloys. In turn, the most relevant diagnostic systems and PFMs (plasma-facing materials) will be described, all accompanied by the corresponding justification for the selection of the materials as well as their main characteristics. Finally, an outlook will be provided on future material development activities to be carried out during the next phase of the conceptual design for DEMO, which is highly dependent on the success of the IFMIF-DONES facility, whose design, operation and objectives are also described in this paper.

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Section: Structural Materialsmentioning

confidence: 99%

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Alba¹,

Rodríguez²,

Cerdeira³

2022

Materials

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“…Furthermore, the minimum insulation thicknesses required for the DIV PFU and DIV CAS feeding pipes to prevent excessive heat losses toward the environment have been calculated for the ex-vessel PHTS pipework up to the vacuum boundary of the upper port annex (at Bio-shield level). Insulation material has been preliminary selected to be microporous insulation Microtherm R SLATTED [20] according to what has been done recently within the context of the ITER TBM programme [21] and to the available diameters from the Microtherm R catalogue. In particular, the calculated thicknesses range from 7 mm to 10 mm for the DIV PFU PHTS piping and from 14 mm to 20 mm for the DIV CAS PHTS piping.…”

Section: Pipe Materials and Thermal Insulationmentioning

confidence: 99%

Pre-conceptual design of EU-DEMO divertor primary heat transfer systems

Vallone

Barucca

Basile

et al. 2021

Fusion Engineering and Design

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“…The Dynamic Probabilistic Risk Analysis (DPRA) approach solves this fundamental lack of standard PRA methodologies, ensuring improved outstanding quality and accuracy. A dynamic event tree analysis has been performed for an ex-vessel Loss Of Coolant Accident (LOCA) occurring in the main loop of the ITER Water Cooled Lithium Lead Test Blanket System (WCLL TBS) [4]. This test-case analysis has been focused on investigating the plasma ramp-down and the SIC-2 triggering time.…”

Section: Introductionmentioning

confidence: 99%

Dynamic Event Tree Analysis as a Tool for Risk Assessment in Nuclear Fusion Plants Using RAVEN and MELCOR

D’Onorio

Glingler

Giannetti

et al. 2022

IEEE Trans. Plasma Sci.

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In the broad framework of the nuclear power plants industry, the dynamic probabilistic risk assessment could answer the time dependence deficiency of the event tree and fault tree analysis. The basic event tree approach relies on experts' pre-constructed accident sequences without exploring the time-dependent nature of an accident scenario, which could strongly affect the accident sequence. Conversely, effects of events timing can be studied adopting a Dynamic Event Tree (DET) approach. Developing a DET methodology requires integrating a system code capable of replicating an accident scenario and a logic-driver code able to generate the event tree sequence, trigger plant safety systems, and manage other relevant events throughout the simulation. For this purpose, MELCOR and RAVEN have been coupled through a Python script developed by the Sapienza University of Rome to perform dynamic event tree studies during accident transients in fusion and fission reactors. RAVEN is a software tool developed at the Idaho National Laboratory (INL) to act as a control logic driver and post-processing tool for different applications. MELCOR for fusion is a fully integrated design basis and severe accident code that simulates thermal-hydraulic behavior and self-consistently accounting for aerosol transport in nuclear facilities and reactor cooling systems for the evaluation of the source term in fusion reactors. The coupling between these codes will provide a wide range of NPP risk assessment analyses, establishing new best practices. In this work, a preliminary dynamic event tree study has been performed, selecting as initiating event an ex-vessel LOCA in the WCLL Test Blanket System to be tested in ITER. Time-dependent parameters such as the intervention of the plasma shutdown system and the closure of the main system isolation valves have been sampled to study evolving system scenarios.

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Overview of recent ITER TBM Program activities

Cited by 66 publications

References 27 publications

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Pre-conceptual design of EU-DEMO divertor primary heat transfer systems

Dynamic Event Tree Analysis as a Tool for Risk Assessment in Nuclear Fusion Plants Using RAVEN and MELCOR

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