ITER TBM Program and associated system engineering

Giancarli, L.; Ahn, Min Cheol; Bonnett, I.; Boyer, Claudine; Chaudhuri, Paritosh; Davis, W. Jr.; Dell’Orco, G.; Iseli, Markus; Michling, R.; Nevière, J.-C.; Romain, P.; Poitevin, Y.; Ricapito, I.; Schneiderova, Iva; Sexton, Louis; Tanigawa, Hisashi; Tonqueze, Y. Le; Laan, J.G. van der; Wang, Xiaoyu; Yoshino, R.

doi:10.1016/j.fusengdes.2018.04.014

Cited by 39 publications

(10 citation statements)

References 11 publications

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“…Just as an example, a DEMO with a fusion power of about 2 GW will consume circa 111 kg of tritium per full power year (fpy), and this clearly underscores the indispensable requirement for the breeding blanket to produce and enable extraction of the bred tritium to achieve tritium self-sufficiency. It should also be kept in mind that ITER operation will largely use up currently known civilian stocks of tritium, from CANDU-type fission reactors, and that tritium supply considerations are very important to define the implementation timeline of a DEMO device, which must breed tritium from the very beginning and use a significant amount of tritium (5-15 kg) for start-up operation [61,62]. This points to the urgent need to monitor the future availability of tritium and to understand the impact on limited resources on the timeline of DEMO.…”

Section: Breeding Blanketmentioning

confidence: 99%

Overview of the DEMO staged design approach in Europe

Federici¹,

Bachmann²,

et al. 2019

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This paper describes the status of the pre-conceptual design activities in Europe to advance the technical basis of the design of a DEMOnstration Fusion Power Plant (DEMO) to come in operation around the middle of this century with the main aims of demonstrating the production of few hundred MWs of net electricity, the feasibility of operation with a closedtritium fuel cycle, and maintenance systems capable of achieving adequate plant availability. This is expected to benefit as much as possible from the ITER experience, in terms of design, licensing, and construction. Emphasis is on an integrated design approach, based on system engineering, which provides a clear path for urgent R&D and addresses the main design integration issues by taking account critical systems interdependencies and inherent uncertainties of important design assumptions (physics and technology). A design readiness evaluation, together with a technology maturation and down selection strategy are planned through structured and transparent Gate Reviews. By embedding industry experience in the design from the beginning it will ensure that early attention is given to technology readiness and industrial feasibility, costs, maintenance, power conversion, nuclear safety and licensing aspects.

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Section: Breeding Blanketmentioning

confidence: 99%

Overview of the DEMO staged design approach in Europe

Federici¹,

Bachmann²,

et al. 2019

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“…Considering the Breeding Blanket (BB) design concept for Demonstration (DEMO) fusion reactor, it turns out that it carries on three major roles: First, to face with the plasma and transfer the extracted heat to the Primary Heat Transfer System (PHTS); Second, to regenerate (breed) the tritium which is consumed in the fusion reaction in order to ensure the tritium self-sufficiency; Third, to provide a sufficient shielding against the radioactive material and heat. Water-Cooled Lead Lithium (WCLL BB) is considered as one of the two (HCPB and WCLL) candidates for the European DEMO nuclear fusion reactor [1], [2], and will be tested during ITER operation through the Test Blanket Module (TBM) program [3]. Since WCLL BB modules are the first indirectly plasma facing in-vessel component, the design characteristics of it can significantly change the safety response of the whole DEMO reactor system Errore.…”

Section: Introductionmentioning

confidence: 99%

Post-test analysis of Series D experiments in LIFUS5/Mod3 facility for SIMMER code validation of WCLL-BB In-box LOCA

Moghanaki

Galleni

Eboli

et al. 2021

Fusion Engineering and Design

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“…Since BB is the first contacting medium, which indirectly interacts with the plasma surface, the features of the blanket system can highly affect the safety performance of the DEMO reactor [1]. Water-Cooled Lithium-Lead (WCLL BB) is considered among the four alternative options (which is newly shortened to two promising options as HCPB and WCLL) for the European DEMO nuclear fusion reactor [2], [3], which will be tested during ITER operation through the Test Blanket Module (TBM) program [4].…”

Section: Introductionmentioning

confidence: 99%