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APPLICATION OF NON-TRANSFER-TYPE PLASMA HEATING TECHNOLOGY FOR CORE-MATERIAL-RELOCATION TESTS IN BWR SEVERE ACCIDENT CONDITIONS

[+] Author and Article Information
Yuta Abe

Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Higashi-Ibaraki-gun, Ibaraki-ken, 311-1393, Japan
abe.yuta@jaea.go.jp

Ikken Sato

Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Higashi-Ibaraki-gun, Ibaraki-ken, 311-1393, Japan
sato.ikken@jaea.go.jp

Toshio Nakagiri

Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Higashi-Ibaraki-gun, Ibaraki-ken, 311-1393, Japan
nakagiri.toshio@jaea.go.jp

Akihiro Ishimi

Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Higashi-Ibaraki-gun, Ibaraki-ken, 311-1393, Japan
ishimi.akihiro@jaea.go.jp

Yuji Nagae

Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Higashi-Ibaraki-gun, Ibaraki-ken, 311-1393, Japan
nagae.yuji@jaea.go.jp

1Corresponding author.

ASME doi:10.1115/1.4038911 History: Received September 29, 2016; Revised December 19, 2017

Abstract

A new experimental program using non-transfer type plasma heating is under consideration in JAEA to clarify the uncertainty on core-material relocation (CMR) behavior of BWR. In order to confirm the applicability of this new technology, authors performed preparatory plasma heating tests using small-scale test pieces (107 mm x 107 mm x 222 mmh). An excellent perspective in terms of applicability of the non-transfer plasma heating to melting high melting-temperature materials such as ZrO2 has been obtained. In addition, molten pool was formed at the middle height of the test piece indicating its capability to simulate the initial phase of core degradation behavior consistent with the real UO2 fuel Phebus-FPT tests. Furthermore, application of EPMA, SEM/EDX and X-ray CT led to a conclusion that the pool formed consisted mainly of Zr with some concentration of oxygen which tended to be enhanced at the upper surface region of the pool. Based on these results, an excellent perspective in terms of applicability of the non-transfer plasma heating technology to the Severe Accident (SA) experimental study was obtained. Keywords: Fukushima Daiichi decommissioning, core-material relocation (CMR), non-transfer type plasma heating, X-ray CT

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