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Technical Papers

Experimental Investigation of Melt Coolability Under Bottom Injection: Effects of Melt Volume, Melt Composition, Nozzle Diameter, and Inlet Pressure

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Pages 306-318 | Received 20 Oct 2016, Accepted 08 Mar 2017, Published online: 23 May 2017

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Read on this site (3)

Samyak S. Munot, Arun K. Nayak & Jyeshtharaj B. Joshi. (2024) CFD Modeling and Analysis of a Heat-Generating Melt Pool Under External Vessel Cooling and Top Flooding. Nuclear Technology 210:6, pages 985-1002.
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Samyak S. Munot & Arun K. Nayak. (2024) CFD Simulation of Melt Pool Coolability in a Simulated Core Catcher Model. Nuclear Science and Engineering 198:3, pages 735-748.
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Sunil Kumar Jatav, Vijay Kumar Pandey, Parimal P. Kulkarni, Arun K. Nayak, Upender Pandel & Rajendra K. Duchaniya. (2022) Effect of Nozzle Diameter on Quenching Behavior of Simulant Material CaO-Fe2O3 Under Bottom Flooding Conditions. Nuclear Technology 208:11, pages 1756-1768.
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Articles from other publishers (5)

S. S. Munot, A. K. Nayak & J. B. Joshi. (2022) Study on Heat Transfer Behavior in a Scaled Down Core Catcher using Simulant Corium Having Indirect Cooling and (Quasi) Volumetric Heat Source. Thermal Engineering 69:5, pages 336-345.
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Samyak S. Munot, Arun K. Nayak & Jyeshtharaj B. Joshi. (2021) Experimental investigations on melt coolability with simulated decay heat—The influence of delay time in flooding. Heat Transfer 51:1, pages 257-273.
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Vijay Kumar Pandey, Sunil K. Jatav, U. Pandel & Rajendra Kumar Duchaniya. (2020) Experimental investigation of quenching behavior of simulant material CaO-Fe2O3 under bottom flooding with the effect of melt volume. Nuclear Engineering and Design 367, pages 110784.
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Sunil Kumar. Jatav, Vijay K. Pandey, Parimal P. Kulkarni, Arun K. Nayak, Upender. Pandel & Rajendra K. Duchaniya. (2020) Effect of Air-quenching on properties of CaO-Fe 2 O 3 and CaO-B 2 O 3 simulant materials for nuclear reactor . Journal of Physics: Conference Series 1455:1, pages 012032.
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Pradeep Pandey, Parimal P. Kulkarni, Arun Nayak & Sumit V. Prasad. (2019) Evaluation of Dump Tank Coolability in PHWRs During Late-Phase Severe Accident. Journal of Nuclear Engineering and Radiation Science 5:4.
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