Published 2014 | Version v1
Miscellaneous

An experimental study on in-vessel retention strategy by external reactor vessel cooling with liquid metal

  • 1. School of Mechanical and Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST), Ulsan (Korea, Republic of)

Description

The present work ultimately aims to develop the IVR-ERVC (In-Vessel Retention through External Reactor Vessel Cooling) system with enough thermal margin adopting liquid metal coolant as the severe accident mitigation system even for high power reactor. For the purpose, the conceptual design of IVR-ERVC with liquid metal is evaluated by performing an experimental campaign for a scaled facility. The specific geometry was devised to contain the liquid metal coolant facing with water through the container wall. Through this system, the heat transfer area is enlarged up to 2 times compared to the original area of the reactor vessel. This effect is also named as 'liquid metal fin' in the current study. Improved heat transfer or reduced heat flux including large drop of focusing effect was confirmed by experimental results for a small-scaled facility to simulate the boiling phenomena under IVR-ERVC condition. It was found that significant reduction of focusing effect by liquid metal and extended surface area guarantee enough margin of successful IVR-ERVC without CHF issue even for large-sized power reactors. (author)

Part of:
Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)

Additional details

Publishing Information

Imprint Title
Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)
Imprint Pagination
2846 p.
Journal Page Range
10 p.

Conference

Title
10. international topical meeting on nuclear thermal hydraulics, operation and safety
Acronym
NUTHOS-10
Dates
14-18 Dec 2014
Place
Ginowan, Okinawa (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
47077906
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COOLANTS; COOLING SYSTEMS; CORIUM; DESIGN; GALLIUM; HEAT FLUX; LIQUID METALS; REACTOR ACCIDENTS; REACTOR SAFETY; REACTOR VESSELS; REFRIGERANTS; RISK ASSESSMENT; SAFETY MARGINS; TEMPERATURE DISTRIBUTION; THERMOCOUPLES; WATER COOLED REACTORS
Descriptors DEC
ACCIDENTS; CONTAINERS; ELEMENTS; ENERGY SYSTEMS; FLUIDS; LIQUIDS; MEASURING INSTRUMENTS; METALS; REACTORS; SAFETY; WORKING FLUIDS

Optional Information

Notes
Available as USB Flash Memory Data in PDF format. Paper ID: NUTHOS10-1171.pdf; 13 refs., 6 figs., 2 tabs.