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1-6 of 6
Keywords: core disruptive accident
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Proceedings Papers
Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A019, August 8–12, 2022
Paper No: ICONE29-91812
... Abstract A new subassembly-type passive reactor shutdown device is proposed to expand the diversity and robustness of core disruptive accident prevention measures for sodium-cooled fast reactors (SFRs). The device contains pins with a fuel material that is in a solid state during normal...
Proceedings Papers
Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Koharu Kawase, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A013, August 4–6, 2021
Paper No: ICONE28-64099
... the diversity and robustness of prevention measures for core disruptive accidents in sodium-cooled fast reactors. The proposed device contains pins with a fuel material that is kept in the solid state during normal operation but melts into the liquid when its temperature exceeds a prescribed value under...
Proceedings Papers
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A025, August 4–6, 2021
Paper No: ICONE28-64500
..., molten core material is an important issue to achieve in-vessel approximately 9 kg of molten alumina was discharged through a retention during a core disruptive accident (CDA) in sodium- duct of 40 mm in inner diameter into a test vessel (200 mm in cooled fast reactors (SFRs)[1]. During a CDA in SFRs...
Proceedings Papers
Hidemasa Yamano, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama, Hiroyuki Fukuyama, Hideo Higashi, Tsuyoshi Nishi, Hiromichi Ohta, Koji Morita, Kinya Nakamura
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A008, August 4–6, 2021
Paper No: ICONE28-63301
...Abstract Abstract One of the key issues in a core disruptive accident (CDA) evaluation in sodium-cooled fast reactors is eutectic reactions between boron carbide (B 4 C) and stainless steel (SS) as well as its relocation. Such behaviors have never been simulated in CDA numerical analyses...
Proceedings Papers
Hidemasa Yamano, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama, Hiroyuki Fukuyama, Hideo Higashi, Tsuyoshi Nishi, Hiromichi Ohta, Xiaoxing Liu, Koji Morita, Kinya Nakamura
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A007, August 4–5, 2020
Paper No: ICONE2020-16102
...STUDY ON EUTECTIC MELTING BEHAVIOR OF CONTROL ROD MATERIALS IN CORE DISRUPTIVE ACCIDENTS OF SODIUM-COOLED FAST REACTORS: (1) PROJECT OVERVIEW AND PROGRESS UNTIL 2018 Hidemasa Yamano1, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama Japan Atomic Energy Agency (JAEA) 4002...
Proceedings Papers
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A028, August 4–5, 2020
Paper No: ICONE2020-16440
... molten fuel pool accompanied by re-criticality in the event of a core disruptive accident (CDA). It is important to ensure in-vessel retention that keeps and confines damaged core material in the reactor vessel even if the CDA occurs. CDA scenario initiated by Unprotected Loss Of Flow (ULOF), which...
