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Oral presentation

Study on In-Vessel Retention (IVR) of unprotected accident for fast reactor, 8; Assessment of post-disassembly expansion and structural response in ULOF

Onoda, Yuichi; Matsuba, Kenichi; Tobita, Yoshiharu

no journal, ,

no abstracts in English

Oral presentation

Study on In-Vessel Retention (IVR) of unprotected accident for fast reactor, 1; Overview of IVR evaluation in Anticipated Transient without Scram (ATWS)

Suzuki, Toru; Tobita, Yoshiharu; Sakai, Takaaki; Nakai, Ryodai

no journal, ,

no abstracts in English

Oral presentation

Study on In-Vessel Retention (IVR) of unprotected accident for fast reactor, 11; Best estimate and uncertainty assessment of PAMR/PAHR phase in ULOF

Sogabe, Joji; Wada, Yusaku*; Suzuki, Toru*; Tobita, Yoshiharu

no journal, ,

no abstracts in English

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.