An overview of dual coolant Pb–17Li breeder first wall and blanket concept development for the US ITER-TBM design

Wong, C.P.C.; Malang, S.; Sawan, M.E.; Dagher, M.; Smolentsev, S.; Merrill, B.J.; Youssef, M.Z.; Reyes, Susanna; Sze, D.K.; Morley, Neil B.; Sharafat, S.; Calderoni, P.; Sviatoslavsky, G.; Kurtz, Richard J.; Fogarty, P.J.; Zinkle, S.J.; Abdou, Mohamed

doi:10.1016/j.fusengdes.2005.05.012

Cited by 105 publications

(42 citation statements)

References 10 publications

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“…In the DCLL blanket helium under 8 MPa pressure is used to cool the first wall (FW) and blanket structure whereas Pb17Li (LiPb) eutectic (with 90%Li-6 enrichment) is circulated in the poloidal direction inside back channels to both remove heat and breed tritium in these zones [1]. The low-activation ferritic steel FS [2], F82H, is used as the structural material.…”

Section: Introductionmentioning

confidence: 99%

Impact of the SiC FCI in the DCLL blanket module on the nuclear environment inside a Demo reactor configuration

Youssef

Morley

Dagher

2009

2009 23rd IEEE/NPSS Symposium on Fusion Engineering

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Abstract-The effects of the inclusion of the SiC flow channel insert (FCI) in a dual-coolant lithium-lead (DCLL) blanket placed in a representative Demo reactor on various key neutronics parameters are studied. These parameters are: tritium production ratio (TBR), power multiplication (PM), profiles of nuclear heating, peak damage parameters (dpa, helium and hydrogen production rates) in the structure, vacuum vessel and shield, peak heating rate and fast neutron fluence in the TF coils. Various thicknesses and density factors of the FCI are considered. These effects are examined in both radial and toroidal direction by 1-D and 2-D models.

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Section: Introductionmentioning

confidence: 99%

Impact of the SiC FCI in the DCLL blanket module on the nuclear environment inside a Demo reactor configuration

Youssef

Morley

Dagher

2009

2009 23rd IEEE/NPSS Symposium on Fusion Engineering

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“…Ha ≈ O (10 3 ) -O(10 5 ) and Re ≈ 10 5 ), which are sufficiently higher than those in typical laboratory experiments (see [32]). Unlike many previous theoretical studies, we extend our analysis to inertial flows at high Reynolds numbers.…”

Section: Introductionmentioning

confidence: 63%

MHD flow in an insulating rectangular duct under a non-uniform magnetic field

2010

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Followed by a review of previous studies of magnetohydrodynamic (MHD) duct flows in a non-uniform magnetic field at the entry into a magnet (fringing magnetic field), the associated MHD problem is revisited for a particular case of a nonconducting rectangular duct of a small aspect ratio ε = b/a (here, b is the duct half-width in the magnetic field direction, and a is the half-height). The suggested model includes a realistic three-component div-and curl-free fringing magnetic field as well as inertia terms and takes into account the mechanism of electric current exchange between the core of the flow and the Hartmann layers. The original three-dimensional flow equations are reduced to a quasi-two-dimensional (Q2D) form for three basic scalar quantities: the vorticity, the streamfunction and the electric potential. This Q2 D formulation implies that the velocity field in the core region between the two Hartmann layers does not change in the magnetic field direction and thus is twodimensional, while the induced electric current forms both cross-sectional and axial circuits and is essentially three-dimensional. A new parameter R = ε 2 Re/Ha has been identified to characterize the role of inertia in duct flows with insulating walls (Re and Ha stand for the Reynolds and Hartmann numbers). Computations and analytical studies are performed for inertialess (R ≪ 1) and inertial (R ≫ 1) flows at ε = 0.2 for Re up to 300,000 resulting in new scaling laws for typical lengths, velocities, electric current densities and pressure drops, which provide a new theoretical basis for potential applications.

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“…The US technology community is also proposing to further develop a dual-coolant He/lead-lithium (DCLL) [9] first wall and blanket concept (originally developed as part of the ARIES-ST study [10]). The US strategy here is to attempt to improve the performance of the similar EU helium-cooled lead-lithium (HCLL) concept by the addition of a high temperature PbLi self-cooled breeding zone electrically and thermally insulated from the ferritic steel structure by SiC/SiC composite flow channel inserts [11].…”

Section: Dual-coolant Lead-lithium Tbmsmentioning

confidence: 99%