Published October 2013 | Version v1
Miscellaneous

Numerical Analysis of In-Vessel Retention using MARS-Ga for APR1400 under the Ga-based External Reactor Vessel Cooling

  • 1. Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

Description

To stabilize and terminate the severe accident through enhancing the coolability of the degraded core, this paper introduces an approach to avoid heat removal limit by replacing flooding material from the borated water to the liquid metal, gallium. The attractive properties such as the low melting point, high boiling point, and no reaction with water ensure that gallium can play an important role in nuclear safety as an alternative coolant in the gap between the vessel and the vessel insulation. The properties of liquid gallium compared to other materials are indicated. For the investigation on the effect of gallium for IVR-ERVCS, numerical simulation for severe accident in APR 1400 using MARS-LMR was performed. In this study, the numerical analysis of gallium-based IVR-ERVCS using MARS-LMR was performed. The range of temperature distribution in this system was considered as an important factor and then the possibility of ERVC using liquid gallium was confirmed. In addition, It will perform the sensitivity studies for the heat transfer area between liquid gallium and borated water to design the optimum ERVC using liquid gallium

Part of:
Proceedings of the KNS Fall meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS Fall meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2013 Fall meeting of the KNS
Dates
23-25 Oct 2013
Place
Kyungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
45082321
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COOLING; DESIGN; M CODES; MELTING POINTS; NUMERICAL ANALYSIS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR VESSELS; RETENTION; SAFETY; SENSITIVITY
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; MATHEMATICS; PHYSICAL PROPERTIES; POWER REACTORS; REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRANSITION TEMPERATURE; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
10 refs, 4 figs, 2 tabs