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Matsuba, Kenichi; Kamiyama, Kenji; Toyooka, Junichi; Zuev, V. A.*; Kolodeshnikov, A. A.*
Proceedings of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) (USB Flash Drive), 11 Pages, 2017/09
To clarify jet fragmentation and accompanying cooling behaviors of molten core materials discharged into sodium, results of the out-of-pile experiments with a simulant material (Al
O
) were analyzed. The results clarified that while AlO jets were entirely fragmented into smaller particles during their penetration to several tenths of a meter in depth of sodium, an additional significant distance was needed to cool down the particles to the degree that thermal loading on the steel structures could be neglected. Based on the results, it is concluded that in terms of the reduction of thermal load on the lower structures in the reactor vessels, the cooling distance after fragmentation should be treated.
Tobita, Yoshiharu; Kamiyama, Kenji; Tagami, Hirotaka; Matsuba, Kenichi; Suzuki, Toru; Isozaki, Mikio; Yamano, Hidemasa; Morita, Koji*; Guo, L.*; Zhang, B.*
Journal of Nuclear Science and Technology, 53(5), p.698 - 706, 2016/05
Times Cited Count：24 Percentile：90.37(Nuclear Science & Technology)The in-vessel retention (IVR) of core disruptive accident (CDA) is of prime importance in enhancing safety characteristics of sodium-cooled fast reactors (SFRs). In the CDA of SFRs, molten core material relocates to the lower plenum of reactor vessel and may impose significant thermal load on the structures, resulting in the melt through of the reactor vessel. In order to enable the assessment of this relocation process and prove that IVR of core material is the most probable consequence of the CDA in SFRs, a research program to develop the evaluation methodology for the material relocation behavior in the CDA of SFRs has been conducted. This program consists of three developmental studies, namely the development of the analysis method of molten material discharge from the core region, the development of evaluation methodology of molten material penetration into sodium pool, and the development of the simulation tool of debris bed behavior.
Matsuba, Kenichi; Isozaki, Mikio; Kamiyama, Kenji; Tobita, Yoshiharu
no journal, ,
In order to develop an evaluation method of the distance for fragmentation of molten core material discharged into the lower sodium plenum during core disruptive accidents in sodium-cooled fast reactors, a series of experiments on fragmentation behavior of simulated molten materials was carried out. A semi-empirical correlation of the distance for fragmentation was developed from the experimental results.
Kamiyama, Kenji; Matsuba, Kenichi; Isozaki, Mikio; Imaizumi, Yuya; Suzuki, Toru; Emura, Yuki
no journal, ,
no abstracts in English
Emura, Yuki; Matsuba, Kenichi; Isozaki, Mikio; Imaizumi, Yuya; Kamiyama, Kenji
no journal, ,
A series of simulation tests discharging a molten alloy with low-melting point into a shallow water pool is being conducted in order to investigate fuel-coolant interaction and sedimentation behavior of molten core materials on the structure of core inlet coolant plenum in the core disruptive accident of sodium-cooled fast reactors. The present study shows effects of the initial temperature of the molten alloy, the confined coolant volume, etc. on the test results.
Matsuba, Kenichi; Isozaki, Mikio; Toyooka, Junichi; Kamiyama, Kenji; Zuev, V.*; Kolodeshnikov, A.*
no journal, ,
In order to assess the fragmentation behavior of molten core material discharged into the lower sodium plenums during core disruptive accidents in sodium-cooled fast reactors, applicability of empirical correlations of the distance for fragmentation was investigated by comparing the values predicted using a correlation with the results obtained in the experiments where a simulated core material (molten alumina) was discharged into a sodium pool.
Emura, Yuki; Isozaki, Mikio; Matsuba, Kenichi; Kamiyama, Kenji
no journal, ,
In core-disruptive accidents of sodium-cooled fast reactors, molten-core materials are discharged into a lower part of reactor vessel and are mixed with sodium there. In this study, molten stainless steel was poured into sodium and its behavior in the sodium was observed by a visualization system using X-ray.
Igarashi, Kai*; Sakai, Takaaki*; Kato, Shinya; Matsuba, Kenichi; Kamiyama, Kenji
no journal, ,
In order to clarify the accumulation behavior on the core disruptive accident in sodium cooled fast reactors, an analysis for the experiment in which the low-melting point alloy drop into a shallow water pool was conducted by using SIMMER code. In this presentation, the validation result for the analysis geometry model conducted by the comparison of the calculation result and experimental value is presented.
Kato, Shinya; Matsuba, Kenichi; Kamiyama, Kenji; Mikisha, A.*; Akayev, A.*; Vurim, A.*; Baklanov, V.*
no journal, ,
In order to enrich experimental knowledge of discharge behavior of molten core materials through a sodium-filled channel in core disruptive accidents of sodium cooled fast reactors, an out-of-pile experiment was conducted, in which molten alumina was used as a molten-fuel simulant and it penetrated into a sodium-filled channel with an internal structure reducing a flow area. In this presentation, consideration on effects of the internal structure on melt discharge-behavior will be presented based on experimental results.
Kato, Shinya; Matsuba, Kenichi; Kamiyama, Kenji
no journal, ,
no abstracts in English
Matsushita, Hatsuki*; Kobayashi, Ren*; Sakai, Takaaki*; Kato, Shinya; Matsuba, Kenichi; Kamiyama, Kenji
no journal, ,
no abstracts in English
