Experimental and numerical study of phwr specific suspended debris

Journal article

Authors / Editors

Sahoo, Pradeep

Research Areas

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Publication Details

Author list: Dutt N, Sahoo PK

Publisher: Elsevier

Place: LAUSANNE

Publication year: 2018

Journal: Nuclear Engineering and Design (0029-5493)

Journal acronym: NUCL ENG DES

Volume number: 330

Start page: 344

End page: 355

Number of pages: 12

ISSN: 0029-5493

Languages: English-Great Britain (EN-GB)

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Abstract

In 220 MWe Indian Pressurized Heavy Water Reactor (IPHWR), under a postulated scenario of unmitigated Station Black Out (SBO) or a large break Loss of Coolant Accident (LOCA) along with the failure of all heat sinks, the fuel channels are likely to heat up due to un-availability of coolant. These events are called Beyond Design Basis Events (BDBEs) where designed engineered safety feature to be not available. The accident sequence leads to moderator boil-off in Calandria. The postulated boil-off leads to slow un-covering of the channels leading to fuel bundle heat up. The exposed channels in the steam environment are known as suspended debris. The present investigation aims to study the heat up behaviour of a single fuel channel of the Calandria for the 220 MWe PHWR. During moderator boil-off phase, it is postulated that decay heat of submerged fuel channels produce steam and acts as a coolant for the suspended channels forming debris like configuration. Experimental study and numerical simulation have been carried out for one-meter, fuel channel at 0.25%-1% of the decay heat. Numerically predicted temperature profile of the outer surface of CT, PT and fuel pins are validated with experimental results. Numerical results are obtained for total heat flux, radiation heat transfer and heat transfer coefficient of the outer surface of CT. Radiation is found to be the dominant mode of heat transfer and for 0.25-1.0% it contributes between 72 and 79% of total heat transfer. From the numerical study, it is concluded that the fuel bundles of the channel are heated maximum up to 804 degrees C if the decay heat 1% of the rated power. Radiation and convective steam cooling helps to limit the temperature rise of the bundle.

Keywords

IPHWR, LOCA, Submerged fuel channel

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