Depressurization behavior of vacuum vessel pressure suppression systems in fusion reactors at multiple first wall pipe break events

Issue title: Proceedings of the tenth International Symposium on Applied Electromagnetics and Mechanics ISEM-Tokyo

Article type: Research Article

Authors: Takase, K.^{a; *} | Akimoto, H.^a

Affiliations: [a] Japan Atomic Energy Research Institute (JAERI), Tokai-mura, Ibaraki-ken, 319-1195, Japan

Correspondence: [*] Corresponding author: K. Takase, Tel.: +89 29 282 5351; Fax: +89 29 282 6439; E-mail: [email protected]

Abstract: An integrated ICE (Ingress-of-Coolant Event) test facility was constructed to demonstrate that the ITER (International Thermonuclear Experimental Reactor) safety design approach and design parameters for the ICE are adequate. Major objectives of the integrated ICE test facility are to estimate the performance of an integrated pressure suppression system and obtain the validation data for safety analysis codes and clarify the two-phase flow behavior under vacuum. The integrated ICE test facility simulates the ITER components with a scaling factor of 1/1600. The modified TRAC-PF1 code is used to verify the integrated ICE experimental results. From the present study the effectiveness of the ITER pressure suppression system was verified experimentally and analytically, and then, it was clarified quantitatively that the prediction accuracy of the modified TRAC-PF1 code is very high.

DOI: 10.3233/JAE-2002-490

Journal: International Journal of Applied Electromagnetics and Mechanics, vol. 13, no. 1-4, pp. 365-372, 2002