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Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor 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
e-mail: abe.yuta@jaea.go.jp

Ikken Sato

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

Toshio Nakagiri

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

Akihiro Ishimi

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

Yuji Nagae

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

1Corresponding author.

Manuscript received September 29, 2016; final manuscript received December 19, 2017; published online March 5, 2018. Editor: Igor Pioro.

ASME J of Nuclear Rad Sci 4(2), 020901 (Mar 05, 2018) (8 pages) Paper No: NERS-16-1117; doi: 10.1115/1.4038911 History: Received September 29, 2016; Revised December 19, 2017

A new experimental program using nontransfer (NTR) type plasma heating is under consideration in Japan Atomic Energy Agency (JAEA) to clarify the uncertainty on core-material relocation (CMR) behavior of boiling water reactor (BWR). In order to confirm the applicability of this new technology, authors performed preparatory plasma heating tests using small-scale test pieces (107 mm × 107 mm × 222 mm (height)). An excellent perspective in terms of applicability of the NTR 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 fission products (FP) tests. Furthermore, application of electron probe micro-analyzer (EPMA), scanning electron microscope (SEM)/energy dispersive X-ray spectrometry (EDX), and X-ray computed tomography (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 NTR plasma heating technology to the severe accident (SA) experimental study was obtained.

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References

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Figures

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Fig. 1

Test reactor design model and vertical section of melting reactor assembly of test piece (left: birds-eye view, right: vertical sectional)

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Fig. 2

Insulation and containment details surrounding assembled test piece (left: vertical section, right: transverse cross section)

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Fig. 3

Isometric (three-dimensional) exploded assembly view of the test piece

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Fig. 4

Operating power and temperature data history for run-1

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Fig. 5

Test piece of run-1 after heating (tube bundle array, fusing of zirconium alloy tubes, top view, and vertical sectional cut of base)

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Fig. 6

Operating power for run-2 and run-3 and measured temperature for run-2

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Fig. 7

Test piece and SS base of run-2 after heating

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Fig. 8

Test piece of run-3 after heating

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Fig. 9

X-ray CT image of the test piece of run-3 (left: photograph, right: cross-sectional X-ray CT image)

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Fig. 10

Elemental (oxygen: O) mapping result obtained by EPMA, and scanning electron images obtained on the vertical section of molten test piece (run-3)

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Fig. 11

Scanning electron image on the vertical section of upper surface region in the pool

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