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.

References

1.
Sato
,
I.
,
Nakagiri
,
T.
,
Abe
,
Y.
,
Ishimi
,
A.
, and
Nagae
,
Y.
,
2015
, “
An Experimental Program Addressing Core Material Relocation Behavior During Severe Accident Using Non-Transfer Type Plasma Heating
,”
Technical Meeting on Post-Fukushima R&D Strategies and Priorities of IAEA
, Wien, Austria, Dec. 15–18, pp. 1–17.
2.
Luxat, D., Hanophy, J., Kalanich, D., and Wachowiak, R., 2015, “Modular Accident Analysis Program (MAAP)—MELCOR Crosswalk: Phase 1 Study,” Electric Power Research Institute, Palo Alto, CA, EPRI Report No.
3002004449
.https://lwrs.inl.gov/Reactor%20Safety%20Technologies/Crosswalk-phase1-final.pdf
3.
Girault
,
N.
,
Fiche
,
C.
,
Bujan
,
A.
, and
Dienstbier
,
J.
,
2009
, “
Towards a Better Understanding of Iodine Chemistry in RCS of Nuclear Reactors
,”
Nucl. Eng. Des.
,
239
(
6
), pp.
1162
1170
.
4.
Hagen
,
S.
,
Hofmann
,
P.
,
Noack
,
V.
,
Sepold
,
L.
,
Schanz
,
G.
, and
Schumacher
,
G.
,
1997
, “Pre-Oxidised BWR Test CORA-28: Test Results,” Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany, Report No.
FZKA-5571
.https://inis.iaea.org/search/search.aspx?orig_q=RN:29000256
5.
Sepold
,
L.
,
Schanz
,
G.
,
Steinbruck
,
M.
,
Stuckert
,
J.
,
Miassoedov
,
A.
,
Palagin
,
A.
, and
Veshchunov
,
M.
,
2006
, “
Results of the QUENCH-09 Experiment Compared to QUENCH-07 With Incorporation of B4C Absorber
,”
Nucl. Technol.
,
154
(1), pp.
107
116
.
6.
Gauntt
,
R. O.
, and
Humphries
,
L. L.
,
1997
, “Final Results of the XR-2-1 BWR Metallic Melt Relocation Experiment,” Nuclear Regulatory Commission, Washington, DC, Report No.
NUREG/CR-6527
.https://www.osti.gov/scitech/servlets/purl/531083
7.
Kleykamp
,
H.
, and
Pejsa
,
R.
,
1991
, “Chemical X-Ray Diffraction Analysis on Selected Samples From TMI-2 Reactor Core,” Kernforschungszentrum Karlsruhe GmbH, Karlsruhe, Germany, Report No.
KfK-4872
.https://inis.iaea.org/search/search.aspx?orig_q=RN:23000010
8.
Ackermann
,
R. J.
,
Garg
,
S. P.
, and
Rauh
,
E. G.
,
1977
, “
High-Temperature Phase Diagram for the System Zr-O
,”
J. Am. Ceram. Soc.
,
60
(
7–8
), pp.
341
345
.
9.
Fink
,
J. K.
,
Chasnov
,
M. G.
, and
Leibowitz
,
L.
,
1981
, “
Thermophysical Properties of Uranium Dioxide
,”
J. Nucl. Mater.
,
102
(
1–2
), pp.
17
25
.
10.
Hanus
,
G.
,
Sato
,
I.
, and
Iwama
,
T.
,
2016
, “
Computational and Experimental Examination of Simulated Core Damage and Relocation Dynamics of a BWR Fuel Assembly—16013
,”
Waste Management Symposia
(WM 2016), Phoenix, AZ, Mar. 6–10, pp. 1–12.
11.
Ishimi
,
A.
,
Tachi
,
Y.
,
Katsuyama
,
K.
, and
Misawa
,
S.
,
2014
, “X-ray CT Basic Data About Inspection of Irradiated Fuel Assembly,” Japan Atomic Energy Agency, Tokai, Ibaraki, Japan, Report No.
JAEA-Data/Code 2014-012
.https://inis.iaea.org/search/search.aspx?orig_q=rn:48062865
You do not currently have access to this content.