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Safety Analysis Results for ITER In-Vessel Loss of Coolant Events

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Abstract

A number of postulated in-vessel loss of coolant accidents (LOCAs) associated with the first wall and baffle cooling systems of the ITER detailed design have been analyzed for the ITER Non-site Specific Safety Report (NSSR-1). A range of break sizes from one first wall tube break (1.57 × 10−4 m2) to damage to all in-vessel components (0.6 m2 break) have been examined. These events span the ITER event classification from likely events to extremely unlikely events. In addition, in-vessel pipe breaks in combination with bypass of the two confinement barriers through a generic penetration have been examined. In all cases, when the vacuum vessel pressure suppression system is activated, most of the radioactive inventory is carried to the suppression pool where it remains for the duration of the event. Releases in these events are well within ITER release limits.

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Authors and Affiliations

  1. Fusion Safety Program Idaho National Engineering Laboratory, P.O. Box 1625, Idaho Falls, Idaho, 83415-3815

    D. A. Petti, B. J. Merrill, S. T. Polkinghorne, L. C. Cadwallader & R.L. Moore

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  1. D. A. Petti
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  2. B. J. Merrill
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  3. S. T. Polkinghorne
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  4. L. C. Cadwallader
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  5. R.L. Moore
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Petti, D.A., Merrill, B.J., Polkinghorne, S.T. et al. Safety Analysis Results for ITER In-Vessel Loss of Coolant Events. Journal of Fusion Energy 16, 125–131 (1997). https://doi.org/10.1023/A:1022529416554

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  • DOI: https://doi.org/10.1023/A:1022529416554

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