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Journal Articles

A Recent experimental program to evidence in-vessel retention by controlled material relocation during core disruptive accidents of sodium-cooled fast reactors

Matsuba, Kenichi; Kamiyama, Kenji; Toyooka, Junichi; Zuev, V. A.*; Ganovichev, D. A.*; Kolodeshnikov, A. A.*

Proceedings of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-10) (USB Flash Drive), 5 Pages, 2016/11

Molten fuel discharge through control rod guide tubes (CRGTs) is a key process that dominates the termination of core disruptive accidents of sodium-cooled fast reactors, since fuel dispersion from the core contributes to the achievement of both deeper subcriticality in the degraded core and formation of coolable debris bed. Within a framework of a collaborative research program between Japan Atomic Energy Agency and National Nuclear Center of the Republic of Kazakhstan, called EAGLE program, a new experimental program has been started with out-of-pile experiments to clarify the fuel discharge through CRGTs. This paper presents the status of the new program, including experimental results obtained so far.

Oral presentation

Study on the material relocation behavior in the core disruptive accident of FBR

Kato, Shinya; Matsuba, Kenichi; Kamiyama, Kenji

no journal, , 

In order to clarify the event progression and its influential factors in the core disruptive accident of the sodium-cooled fast reactor, JAEA has carried out EAGLE(Experimental Acquisition of Generalized Logic to Eliminate re-criticalities)-3 project with the cooperation of National Nuclear Center of the Republic of Kazakhstan. The result of the out-of-pile test focused on the outflow of the molten-core material through the control rod guide tube will be shown.

Oral presentation

Study on the discharge behavior of molten core materials through the control rod guide tube in the core disruptive accident of SFR

Kato, Shinya; Matsuba, Kenichi; Kamiyama, Kenji; Zuev, V.*; Ganovichev, D.*; Baklanov, V.*

no journal, , 

To clarify the molten material outflow behavior from the reactor core region through the control rod guide tube(CRGT) in the core disruptive accident of SFR, the out-of-pile tests simulating the molten material dropping into the CRGT, they are imitated by the molten alumina and the stainless cup respectively, were conducted. In this presentation, the evaluation result of the tests will be reported.

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