The design of the center core of a spherical tokamak

Colchin, R.J.; Edmonds, P.H.; Galambos, J.; Goranson, P.; Hirshman, S.P.; Uglum, J.R.

doi:10.1109/fusion.1995.534497

Cited by 2 publications

(4 citation statements)

References 3 publications

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“…This gives a total of 61 cooling channels. This case is qualitatively similar to the Colchin et al [7] case shown in Fig. 3(b).…”

Section: Modelingsupporting

confidence: 88%

“…It is desired that this component has an adequate design margin to ensure longpulse operation, which, in turn, requires a thermal-structural analysis to validate the design. Numerous design and analysis studies have been performed and documented for an ST reactor (see [6] and [7], for example). A critical design question for the centerpost is whether internal water cooling channels can adequately control the temperature within the centerpost while preventing high thermal stress gradients within the structure.…”

Section: Introductionmentioning

confidence: 99%

“…Examples of previous studies on the design of cooling channels for an ST centerpost by (a) Song and Nishio[6] and (b) Colchin et al[7].…”

mentioning

confidence: 99%

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Structural Analysis of an Optimally Designed Spherical Tokamak Centerpost

Lumsdaine

Peng

2012

IEEE Trans. Plasma Sci.

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The realization of commercialized fusion power will involve the development of new materials that can withstand the uniquely harsh nuclear fusion environment. Of particular interest are those materials that are closest to the plasma. The combination of thermal loading, neutron damage, material sputtering, and redeposition provides uniquely hostile conditions under which no material testing has yet occurred. An experimental Fusion Nuclear Science Facility is required that will create the environment that simultaneously achieves high-energy neutrons and high ion fluence necessary in order to bridge the gaps from ITER to the realization of a fusion nuclear power plant. One concept for achieving this is a high-duty-cycle spherical tokamak (ST). The centerpost is a critical component of the ST design, as it controls the size of the entire reactor. The centerpost will experience significant thermal loading and thermal gradients from ohmic heating, nuclear heating, and water cooling. Nuclear heating will also produce embrittlement and swelling in the centerpost. In addition to thermal loads, the centerpost must be designed to carry mechanical loads produced from the various magnetic fields (TF, PF, and plasma currents), both steady state and transient. The centerpost temperature must remain low enough to permit water cooling, and stresses must remain low enough so that the centerpost remains structurally sound. This study will focus on the stress analysis of a centerpost optimized to reduce the thermal gradients in the cross section.

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“…This gives a total of 61 cooling channels. This case is qualitatively similar to the Colchin et al [7] case shown in Fig. 3(b).…”

Section: Modelingsupporting

confidence: 88%

Section: Introductionmentioning

confidence: 99%

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Structural Analysis of an Optimally Designed Spherical Tokamak Centerpost

Lumsdaine

Peng

2012

IEEE Trans. Plasma Sci.

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“…2. This type of cooling channel pattern is consistent with previous studies of ST centerpost designs for nuclear facilities [2,6]. The design variables are the radii of the cooling channels (where all channels in one row have the same radius) and the radial position of each row.…”

Section: Optimization Problem Statementmentioning

confidence: 69%