Overview of the ITER TBM Program

Giancarli, L.; Abdou, Mohamed; Campbell, D.J.; Chuyanov, V.A.; Ahn, Min Cheol; Enoeda, Mikio; Pan, C.H.; Poitevin, Y.; Kumar, E. Rajendra; Ricapito, I.; Strebkov, Yu.S.; Suzuki, Satoshi; Wong, P.C.; Zmítko, M.

doi:10.1016/j.fusengdes.2011.11.005

Cited by 206 publications

(76 citation statements)

References 11 publications

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“…Since testing a number of full-size blanket sectors is judged mandatory for the qualification of any blanket concept, the more advanced version of the DCLL blanket, originally tested in the TBM, is later deployed as a full sector in subsequent phase(s) of HTS-FNSF to validate their characteristics and features for DEMO. As noted, this strategy reaches beyond the traditional testing mission of ITER that tests several blanket concepts only in TBMs at lower flux and fluence, but not in other modules [28].…”

Section: Tbm Testing Strategy Configuration and Deliverablesmentioning

confidence: 99%

“…Helium-cooled ceramic breeder blankets could be tested, if needed, in the remaining TBM of the FNSF. Over the past 15 years, the ITER team developed a comprehensive strategy to test such alternate concepts (among others) in the six TBMs of ITER [28]. In the 2000s, the U.S. proposed a DCLL TBM for ITER [33].…”

Section: Tbm Testing Strategy Configuration and Deliverablesmentioning

confidence: 99%

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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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Section: Tbm Testing Strategy Configuration and Deliverablesmentioning

confidence: 99%

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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“…14 The structural material choice for the blanket is less certain 12,13 and a range of materials have been suggested, including vanadium alloys and SiC/SiC composites; [15][16][17] however the most techno-CCFE, Culham Science Centre, Abingdon, Oxon. OX14 3DB, UK *Corresponding author, email mike.gorley@ccfe.ac.uk **The divertor is situated along the bottom of the interior of the reactor structure and is the only point where the plasma is in direct contact with the reactor.…”

Section: Fusion Materials Requirementsmentioning

confidence: 99%

Critical Assessment 12: Prospects for reduced activation steel for fusion plant

Gorley

2015

Materials Science and Technology

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The development of new, high performance reduced activation materials is increasingly recognised as one of the key enabling technologies required for the advancement of civil fusion power. Reduced activation steels are considered the leading materials for fusion reactor blanket structural materials. The manufacturing technologies and database for the current leading reduced activation steels have reached a state of maturity where basic design and implementation can be addressed. However, there remain concerns with these materials due to an incomplete irradiation database and because of their limited operational temperature window. The requirements of these steels along with various proposed methods to improve reduced activation steels are critically assessed, and some indications given on future paths for progress.

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“…Modified lithium orthosilicate (Li 4 SiO 4 ) pebbles with additions of titanium dioxide (TiO 2 ) are developed as a possible tritium breeder [6]. Due to addition of TiO 2 , lithium metatitanate (Li 2 TiO 3 ) was obtainted as a secondary phase [7].…”

Section: Introductionmentioning

confidence: 99%

Luminescence of X-ray induced radiation defects in modified lithium orthosilicate pebbles with additions of titanium dioxide

Cipa¹,

Ķizāne²,

Supe³

et al. 2017

energetika

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Modified lithium orthosilicate (Li 4 SiO 4 ) pebbles with additions of titanium dioxide (TiO 2 ) are designed as a possible tritium breeder ceramic for the helium cooled pebble bed (HCPB) test blanket module. Additions of TiO 2 were chosen to enhance mechanical properties of the tritium breeder pebbles. The formation of radiation defects (RD) in the modified Li 4 SiO 4 pebbles with a different content of TiO 2 was studied by X-ray induced luminescence (XRL) technique. After XRL measurements the accumulated RD were also analyzed by thermally stimulated luminescence (TSL) and electron spin resonance (ESR) spectrometry. XRL spectra consist of several bands with maxima at around 430, 490, 690, 700 and 800 nm. The XRL band with a peak at 490 nm could be associated with intrinsic defects in Li 4 SiO 4 matrix whereas all the other maxima at lower photon energies are the result of the addition of TiO 2 .

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Overview of the ITER TBM Program

Cited by 206 publications

References 11 publications

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

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

Critical Assessment 12: Prospects for reduced activation steel for fusion plant

Luminescence of X-ray induced radiation defects in modified lithium orthosilicate pebbles with additions of titanium dioxide

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