The European breeding blankets development and the test strategy in ITER

Poitevin, Y.; Boccaccini, L.V.; Cardella, A.; Giancarli, L.; Meyder, R.; Diegele, E.; Laesser, R.; Benamati, G.

doi:10.1016/j.fusengdes.2005.06.296

Cited by 50 publications

(25 citation statements)

References 10 publications

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“…Due to the necessity of using structures to maintain blanket and first wall, the initial research showed that the compounds containing liquid lithium had the highest potential for tritium generation. But the materials in these structures could be reduced up to 30 % tritium breeding ratio, while this impact was\10 % for ceramic breeder of Li 4 SiO 4 [8,9].…”

Section: Tbr ¼mentioning

confidence: 99%

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Tritium Breeding Ratio Calculation for ITER Tokamak Using Developed Helium Cooled Pebble Bed Blanket (HCPB)

Soltani

Habibi

2015

J Fusion Energ

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In this paper, neutronic calculations were performed to obtain tritium breeding ratio (TBR) for ITER device using developed helium cooled pebble (HCPB) blanket. The designed blanket module has the following combinations; natural lithium, Li 4 SiO 4 (20 %), beryllium moderator and neutron multiplier. To ensure tritium selfsufficiency, the calculated achievable TBR should be equal to or greater than the required TBR. Simulations have been performed by means of Monte Carlo MCNP-4C code using END/B-VII.1 data library. Results show that TBR of 1.14 is obtained for this new HCPB.

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Section: Tbr ¼mentioning

confidence: 99%

“…T + 4 He + 4:78 MeV ð2Þ 7 Li + n ! T + 4 He þ n À 2:47 MeV ð3Þ Figure 2 shows tritium production cross section versus neutron energy for 6 Li and 7 Li [8]. Because the cross section for 7 Li is lower than 6 Li, if Eq.…”

Section: Hcpb Ceramic Blanketmentioning

confidence: 99%

Tritium Breeding Ratio Calculation for ITER Tokamak Using Developed Helium Cooled Pebble Bed Blanket (HCPB)

Soltani

Habibi

2015

J Fusion Energ

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“…Europe is currently developing two reference breeding blankets for DEMO reactor specifications that will be tested in ITER under the form of test blanket modules (TBMs) [1][2][3]: the helium-cooled lithiumlead (HCLL) concept which uses the eutectic Pb-15.7 Li as both breeder and neutron multiplier, and the ensure simultaneous control on the project scope, time and cost. For that purpose, Europe has achieved a basic review of these fundamental elements and the outcome is summarized in the present paper.…”

Section: Introductionmentioning

confidence: 99%

“…Item (i) also includes blanket R&D to be integrated in TBMs (breeder/multiplier materials development, tritium control and extraction, MHD, etc.). Those activities are not discussed here but are detailed in [1][2][3]. Item (iv) mentioned above is mainly related to the amount and quality of information gained during the tests in ITER.…”

Section: Introductionmentioning

confidence: 99%

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The test blanket modules project in Europe: From the strategy to the technical plan over next 10 years

Poitevin¹,

Boccaccini²,

Dell’Orco³

et al. 2007

Fusion Engineering and Design

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Development and experiments of LiPb coolant technologies for fusion blanket in China

Qunying

Zhu

Team³

2020

Int J Energy Res

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Summary The liquid lithium lead (LiPb) blanket concept has become a promising design for fusion reactor, for example, international thermonuclear experimental reactor (ITER) and the demonstration (DEMO) reactor. To promote the successful application of fusion energy, detailed studies on key issues of the LiPb blanket were performed, such as corrosion behavior, thermal hydraulics and coolant safety etc. Some experimental facilities needed for the key issue studies were designed and developed under the research program. The series LiPb experimental loops, named DRAGON, were developed in China, including the thermal convection loops DRAGON‐I/II/III and the multi‐functional experimental loop DRAGON‐IV. To perform the integrated experiments under the multi‐physical field conditions for DEMO blanket, a dual‐coolant thermal integrated experimental loop DRAGON‐V was built in 2017. It is a multi‐functional test platform for the research and development (R&D) of key issues of liquid LiPb blanket to provide the necessary database for ITER and DEMO. Up to now, a lot of experiments have been performed to investigate the LiPb technologies, such as corrosion behaviors of structural materials both with and without magnetic field, corrosion resistance technology, magneto‐hydrodynamics effect, and interaction between typical coolants during in‐box loss of coolant accident etc. The results will support the R&D of the key techniques and the engineering design for ITER test blanket module and further DEMO.

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The European breeding blankets development and the test strategy in ITER

Cited by 50 publications

References 10 publications

Tritium Breeding Ratio Calculation for ITER Tokamak Using Developed Helium Cooled Pebble Bed Blanket (HCPB)

Tritium Breeding Ratio Calculation for ITER Tokamak Using Developed Helium Cooled Pebble Bed Blanket (HCPB)

The test blanket modules project in Europe: From the strategy to the technical plan over next 10 years

Development and experiments of LiPb coolant technologies for fusion blanket in China

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