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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April 2018
Research-Article
Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions
Yuta Abe,
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
4002 Narita, Oarai-machi, Higashi-Ibaraki-gun,
Ibaraki-ken 311-1393, Japan
e-mail: abe.yuta@jaea.go.jp
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Ikken Sato,
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
4002 Narita, Oarai-machi, Higashi-Ibaraki-gun,
Ibaraki-ken 311-1393, Japan
e-mail: sato.ikken@jaea.go.jp
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Toshio Nakagiri,
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
4002 Narita, Oarai-machi,
Higashi-Ibaraki-gun,
Ibaraki-ken 311-1393, Japan
e-mail: nakagiri.toshio@jaea.go.jp
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Akihiro Ishimi,
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
4002 Narita, Oarai-machi, Higashi-Ibaraki-gun,
Ibaraki-ken 311-1393, Japan
e-mail: ishimi.akihiro@jaea.go.jp
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Yuji Nagae
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
4002 Narita, Oarai-machi, Higashi-Ibaraki-gun,
Ibaraki-ken 311-1393, Japan
e-mail: nagae.yuji@jaea.go.jp
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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
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
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
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
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
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. Apr 2018, 4(2): 020901 (8 pages)
Published Online: March 5, 2018
Article history
Received:
September 29, 2016
Revised:
December 19, 2017
Citation
Abe, Y., Sato, I., Nakagiri, T., Ishimi, A., and Nagae, Y. (March 5, 2018). "Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions." ASME. ASME J of Nuclear Rad Sci. April 2018; 4(2): 020901. https://doi.org/10.1115/1.4038911
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