Experimental investigations on melt coolability with simulated decay heat—The influence of delay time in flooding

Author:

Munot Samyak S.12,Nayak Arun K.12,Joshi Jyeshtharaj B.13

Affiliation:

1. Homi Bhabha National Institute, Anushakti Nagar Mumbai Maharashtra India

2. Reactor Engineering Division, Reactor Design and Development Group, Bhabha Atomic Research Centre Mumbai Maharashtra India

3. Department of Chemical Engineering Institute of Chemical Technology Mumbai Maharashtra India

Publisher

Wiley

Subject

Fluid Flow and Transfer Processes,Condensed Matter Physics

Reference40 articles.

1. BonnetJ‐M CrangaM VolaDi et al. State‐of‐the‐Art Report on Molten Corium Concrete Interaction and Ex‐Vessel Molten Core Coolability. Nuclear Energy Agency of the OECD (NEA); 2017.http://inis.iaea.org/search/search.aspx?orig_q=RN:48099100

2. SidorovAS NedorezovAB RogovMF et al. The device for core melt localization at the Tyan'van nuclear power station with a VVER‐1000 reactor; Thermal Engineering2001;48:707‐712.

3. Core melt stabilization concepts for existing and future LWRS and associated research and development needs;Fischer M;Nucl Technol,2016

4. Kuczera B. R D activities on safety aspects of future PWR plants performed at KfK.Nucl. Saf. U. S.https://www.osti.gov/biblio/7109118

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