Highly radiation-resistant vacuum impregnation resin systems for fusion magnet insulation

Fabian, P. E.; Munshi, N. A.; Denis, Rodrigue

doi:10.1063/1.1472555

Cited by 39 publications

(26 citation statements)

References 4 publications

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“…These could be removed and replaced with the centre column, but are still a critical item since they are so closely coupled to the divertor design. It is suggested that the coil be insulated with cyanate-ester (CE) impregnated glass fibre [28] which has improved radiation resistance compared to conventional epoxy-resins [29]. The gamma flux in the CTF design above is, however, higher than the ITER reference level for coil insulation.…”

Section: Insulating the Divertor Coilsmentioning

confidence: 98%

Spherical tokamaks: Present status and role in the development of fusion power

Morris

Akers

Counsell

et al. 2005

Fusion Engineering and Design

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Section: Insulating the Divertor Coilsmentioning

confidence: 98%

Spherical tokamaks: Present status and role in the development of fusion power

Morris

Akers

Counsell

et al. 2005

Fusion Engineering and Design

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“…The epoxy currently being used in coils made for the LARP as well as Nb 3 Sn magnets at Fermilab is CTD-101K [6].…”

Section: Sample Preparationmentioning

confidence: 99%

TESTS OF INSULATION SYSTEMS FOR Nb3SN WIND AND REACT COILS

Bossert¹,

Ambrosio²,

Andreev³

et al. 2008

AIP Conference Proceedings

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Tests were performed to assess the viability of several cable insulation systems for use in Nb 3 Sn accelerator magnets. Insulated stacks of cables were subjected to reaction cycles commonly used for Nb 3 Sn coils. After reaction and epoxy impregnation, current leakage between turns was measured at pressures up to 180 MPa and turn-to-turn potentials up to 500V. Systems consisting of S-2 glass, ceramic fiber, and E-glass were tested. Several methods of applying the insulation were incorporated, including sleeves and various spiral wrapped configurations. Methods of sample preparation and testing are described and results are reported.

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“…To demonstrated that these new cyanate ester insulation materials can withstand significantly higher irradiation doses than epoxies [3], [4]. These materials have also demonstrated the necessary adhesive strength to ensure that the insulation remains well adhered to the conductor at cryogenic and elevated temperatures [5], [6].…”

Section: Introductionmentioning

confidence: 97%

Shear Strengths of Copper/Insulation Interfaces After In-Core Reactor Irradiations

Grandlienard

Hooker

Fabian

et al. 2007

IEEE Trans. Appl. Supercond.

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The adhesive shear strengths of copper/insulation interfaces were evaluated using a novel specimen design in which thin copper foils were embedded in laminate structures. In each instance, the copper surface was either chemically or physically treated prior to laminate fabrication. Once produced, the specimens were subjected to in-core reactor irradiations providing total radiation doses of 10, 22, and 100 MGy with a gamma/neutron ratio representative of conditions in fusion systems. Post-irradiation short-beam-shear tests indicate that the best-performing copper treatments retain 65-70% of their original interfacial shear strength at 76 K after receiving a total dose of 100 MGy. Previous findings showed that the initial adhesive strength could be improved through the use of copper surface treatments, and these results confirm that the copper/insulation interface remains strong after exposure to high-radiation environments.

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Highly radiation-resistant vacuum impregnation resin systems for fusion magnet insulation

Cited by 39 publications

References 4 publications

Spherical tokamaks: Present status and role in the development of fusion power

Spherical tokamaks: Present status and role in the development of fusion power

TESTS OF INSULATION SYSTEMS FOR Nb3SN WIND AND REACT COILS

Shear Strengths of Copper/Insulation Interfaces After In-Core Reactor Irradiations

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