Fusion Nuclear Science Facility (FNSF) before Upgrade to Component Test Facility (CTF)

Peng, Yi; Canik, J.; Diem, S. J.; Milora, S.L.; Park, J.M.; Sontag, A. C.; Fogarty, P.J.; Lumsdaine, Arnold; Murakami, M.; Burgess, T.; Cole, M. J.; Katoh, Yutai; Korsah, K.; Patton, B.D.; Wagner, John C.; Yoder, G.L.; Stambaugh, R.D.; Staebler, G. M.; Kotschenreuther, M.; Valanju, P.; Mahajan, S. M.; Sawan, M.E.

doi:10.13182/fst60-441

Cited by 32 publications

(27 citation statements)

References 19 publications

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“…It is the purpose of this work to characterize and understand the causes of this collisionality dependence. This underlying dependence could potentially influence strongly the design and construction of an ST-based Fusion Nuclear Science Facility (FNSF), 11,12 as this class device will operate at collisionalities at least one order of magnitude lower than the operating range of NSTX in this parameter.…”

Section: -3mentioning

confidence: 99%

The dependence of H-mode energy confinement and transport on collisionality in NSTX

et al. 2013

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Understanding the dependence of confinement on collisionality in tokamaks is important for the design of next-step devices, which will operate at collisionalities at least one order of magnitude lower than in present generation. A wide range of collisionality has been obtained in the National Spherical Torus Experiment (NSTX) by employing two different wall conditioning techniques, one with boronization and between-shot helium glow discharge conditioning (HeGDC+B), and one using lithium evaporation (Li EVAP). Previous studies of HeGDC+B plasmas indicated a strong and favorable dependence of normalized confinement on collisionality. Discharges with lithium conditioning discussed in the present study generally achieved lower collisionality, extending the accessible range of collisionality by almost an order of unity. While the confinement dependences on dimensional, engineering variables of the HeGDC+B and Li EVAP datasets differed, collisionality was found to unify the trends, with the lower collisionality lithium conditioned discharges extending the trend of increasing normalized confinement time with decreasing collisionality when other dimensionless variables were held as fixed as possible. This increase of confinement with decreasing collisionality was driven by a large reduction in electron transport in the outer region of the plasma. This result is consistent with gyrokinetic calculations that show microtearing and Electron Temperature Gradient modes to be more stable for the lower collisionality discharges. Ion transport, near neoclassical at high collisionality, became more anomalous at lower collisionality, possibly due to the growth of hybrid TEM/KBM modes in the outer regions of the plasma.

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Section: -3mentioning

confidence: 99%

The dependence of H-mode energy confinement and transport on collisionality in NSTX

et al. 2013

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“…While there are many versions of FNSFs, we consider here three representative ST-FNSF designs as shown in Table III. FNSF-I represents the ORNL-led design, 73 FNSF-II represents the PPPLled design, 74 and FNSF-III represents the Culham-led design. 75 The neutron wall loading W L ¼ 1 MW/m 2 is assumed for the FNSF design point.…”

mentioning

confidence: 99%

Recent progress on spherical torus research

Ono

Kaita

2015

Physics of Plasmas

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The spherical torus or spherical tokamak (ST) is a member of the tokamak family with its aspect ratio (A = R0/a) reduced to A ∼ 1.5, well below the normal tokamak operating range of A ≥ 2.5. As the aspect ratio is reduced, the ideal tokamak beta β (radio of plasma to magnetic pressure) stability limit increases rapidly, approximately as β ∼ 1/A. The plasma current it can sustain for a given edge safety factor q-95 also increases rapidly. Because of the above, as well as the natural elongation κ, which makes its plasma shape appear spherical, the ST configuration can yield exceptionally high tokamak performance in a compact geometry. Due to its compactness and high performance, the ST configuration has various near term applications, including a compact fusion neutron source with low tritium consumption, in addition to its longer term goal of an attractive fusion energy power source. Since the start of the two mega-ampere class ST facilities in 2000, the National Spherical Torus Experiment in the United States and Mega Ampere Spherical Tokamak in UK, active ST research has been conducted worldwide. More than 16 ST research facilities operating during this period have achieved remarkable advances in all fusion science areas, involving fundamental fusion energy science as well as innovation. These results suggest exciting future prospects for ST research both near term and longer term. The present paper reviews the scientific progress made by the worldwide ST research community during this new mega-ampere-ST era.

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“…Prior to DEMO construction, fusion power plant components and subsystems must be tested in a dedicated facility with a fusion-relevant environment. A number of proposals have been made in the U.S. for an FNSF type device [7][8][9][10][11] to enable integrated testing and development of fusion technologies under prototypical fusion conditions. Such tokamak and spherical tokamak (ST) facilities will display the complex integration of fusion components and subsystems in relevant fusion environment: 14 MeV neutrons, surface and volumetric heating, helium and hydrogen generation in materials, relevant stresses, high pressures and temperatures with significant gradients, and strong magnetic fields.…”

Section: Introductionmentioning

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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Fusion Nuclear Science Facility (FNSF) before Upgrade to Component Test Facility (CTF)

Cited by 32 publications

References 19 publications

The dependence of H-mode energy confinement and transport on collisionality in NSTX

The dependence of H-mode energy confinement and transport on collisionality in NSTX

Recent progress on spherical torus research

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

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