Progresses and challenges in supporting activities toward a license to operate European TBM systems in ITER

Poitevin, Y.; Ricapito, I.; Zmítko, M.; Tavassoli, F.; Thomas, N.M.; Dinechin, G. de; Bucci, Philippe; Rey, J.; Ibarra, Á.; Panayotov, D.; Giancarli, L.; Calderoni, P.; Galabert, Jose; Vallory, Joelle; Aiello, A.

doi:10.1016/j.fusengdes.2014.03.071

Cited by 24 publications

(7 citation statements)

References 20 publications

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“…• validate and calibrate the design tools and the database used in the blanket design process including neutronics, electromagnetics, heat transfer and hydraulics; • generate data to support the demonstration of the tritium breeding capability and verify on-line tritium recovery and control systems to ultimately enable the extrapolation to a full size blanket; • provide essential information on nuclear licensing of BB components with regard in particular to structural integrity assessment and manufacturing techniques [10]. • demonstrate the integral performances of the HCLL BB concept in a fusion relevant environment.…”

Section: Hcll-tbm Design Features and Relevance For The Design Of Dem...mentioning

confidence: 99%

“…However, because of the specificities of the fusion environment and the peculiarities of EUROFER97 mechanical properties, there is no single validated set of design rules available for the BB components [21]. Appropriate design criteria are in this case needed and development of the RCC-MRx nuclear Codes and Standards (C&S) [22] is underway in the framework of the TBM program [10]. The return of experience from the TBM licensing process will also provide essential feedback with respect to regulation requirements that will also impact the DEMO design.…”

Section: Additional Information Expected From the Tbm Program With Di...mentioning

confidence: 99%

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Design of the helium cooled lithium lead breeding blanket in CEA: from TBM to DEMO

et al. 2017

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The helium cooled lithium lead (HCLL) blanket concept was originally developed in CEA at the beginning of 2000: it is one of the two European blanket concepts to be tested in ITER in the form of a test blanket module (TBM) and one of the four blanket concepts currently being considered for the DEMOnstration reactor that will follow ITER. The TBM is a highly optimized component for the ITER environment that will provide crucial information for the development of the DEMO blanket, but its design needs to be adapted to the DEMO reactor. With respect to the TBM design, reduction of the steel content in the breeding zone (BZ) is sought in order to maximize tritium breeding reactions. Different options are being studied, with the potential of reaching tritium breeding ratio (TBR) values up to 1.21. At the same time, the design of the back supporting structure (BSS), which is a DEMO specific component that has to support the blanket modules inside the vacuum vessel (VV), is ongoing with the aim of maximizing the shielding power and minimizing pumping power. This implies a re-engineering of the modules' attachment system. Design changes however, will have an impact on the manufacturing and assembly sequences that are being developed for the HCLL-TBM. Due to the differences in joint configurations, thicknesses to be welded, heat dissipation and the various technical constraints related to the accessibility of the welding tools and implementation of non-destructive examination (NDE), the manufacturing procedure should be adapted and optimized for DEMO design. Laser welding instead of TIG could be an option to reduce distortions. The time-of-flight diffraction (TOFD) technique is being investigated for NDE. Finally, essential information expected from the HCLL-TBM program that will be needed to finalize the DEMO design is discussed.

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Section: Hcll-tbm Design Features and Relevance For The Design Of Dem...mentioning

confidence: 99%

Section: Additional Information Expected From the Tbm Program With Di...mentioning

confidence: 99%

Design of the helium cooled lithium lead breeding blanket in CEA: from TBM to DEMO

et al. 2017

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“…In the 2000s, the U.S. proposed a DCLL TBM for ITER [33]. A number of deliverables were produced, addressing the different physical phenomena in ITER TBMs and how the data could be extrapolated to DEMO conditions [34][35][36]. Other related activities focused on the development of sensors for ITER TBMs and the associated strategies [37].…”

Section: Tbm Testing Strategy Configuration and Deliverablesmentioning

confidence: 99%

TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO

et al. 2016

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Abstract:The qualification and validation of nuclear technologies are daunting tasks for fusion demonstration (DEMO) and power plants. This is particularly true for advanced designs that involve harsh radiation environment with 14 MeV neutrons and high-temperature operating regimes. This paper outlines the unique qualification and validation processes developed in the U.S., offering the only access to the complete fusion environment, focusing on the most prominent U.S. blanket concept (the dual cooled PbLi (DCLL)) along with testing new generations of structural and functional materials in dedicated test modules. The venue for such activities is the proposed Fusion Nuclear Science Facility (FNSF), which is viewed as an essential element of the U.S. fusion roadmap. A staged blanket testing strategy has been developed to test and enhance the DCLL blanket performance during each phase of FNSF D-T operation. A materials testing module (MTM) is critically important to include in the FNSF as well to test a broad range of specimens of future, more advanced generations of materials in a relevant fusion environment. The most important attributes for MTM are the relevant He/dpa ratio (10-15) and the much larger specimen volumes compared to the 10-500 mL range available in the International Fusion Materials Irradiation Facility (IFMIF) and European DEMO-Oriented Neutron Source (DONES).

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“…Testing the tritium breeding modules (TBM) in ITER [1], and the need to include them in the ITER licensing [2], offers a unique opportunity for further development and validation of the methodology for DEMO breeder blanket (BB) accident analysis [3][4][5][6][7]. The safety approach and accident analysis methodology for ITER is very well defined, as demonstrated by the successful construction licensing [8].…”

Section: Introductionmentioning

confidence: 99%

Methodology for accident analyses of fusion breeder blankets and its application to helium-cooled pebble bed blanket

Panayotov

Grief²,

Merrill

et al. 2016

Fusion Engineering and Design

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Progresses and challenges in supporting activities toward a license to operate European TBM systems in ITER

Cited by 24 publications

References 20 publications

Design of the helium cooled lithium lead breeding blanket in CEA: from TBM to DEMO

Design of the helium cooled lithium lead breeding blanket in CEA: from TBM to DEMO

TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO

Methodology for accident analyses of fusion breeder blankets and its application to helium-cooled pebble bed blanket

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