Published May 2017 | Version v1
Miscellaneous

A Study of Nuclear Reactor Pressure Vessel Lower Head Penetration using Numerical Analysis

  • 1. Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)
  • 2. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

Heat flux from the molten core heats up the pressure vessel inside and melts the inside penetrations and the welding zones. When a welding zone is melted, penetration tube ejection or rupture can occur. In this situation, the only mechanism that held the penetration fixed is the friction force between penetration tube and vessel hole. In that case, the bonding force due to the contact is influenced by the friction force between the tube and the lower vessel. This is due to the differences in thermal expansion experienced in the high temperature environment after the re-location of the molten core. In this study, a numerical analysis using ANSYS 17.1 Release 17.1 was performed to investigate the contact status due to thermal expansion between the penetration tube and the lower vessel. Three major nuclear accidents, i.e., Large Break Loss-of-Coolant Accident (LBLOCA), Station Black Out (SBO), and Total Loss of Feed-Water (TLOFW), were considered as part of the study. Results indicated that when a severe accident occurs, the inside of a penetration is initially heated up. Later, the upper part of inner vessel and the welding zone of tube No.4 are heated up. Because of the heat input and thermal expansion, contacts between the vessel and tubes occur. This contact was found to increase over time. It is probable that the tubes do not eject because of the friction forces.

Part of:
Proceedings of the KNS 2017 Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2017 Spring Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[4 p.]

Conference

Title
2017 Spring Meeting of the KNS
Dates
17-19 May 2017
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
49050402
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BONDING; FEEDWATER; FRICTION; HEAT FLUX; LOSS OF COOLANT; NUMERICAL ANALYSIS; PRESSURE VESSELS; REACTOR VESSELS; RUPTURES; THERMAL EXPANSION; TUBES; WELDING
Descriptors DEC
ACCIDENTS; CONTAINERS; EXPANSION; FABRICATION; FAILURES; HYDROGEN COMPOUNDS; JOINING; MATHEMATICS; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; WATER

Optional Information

Notes
6 refs, 8 figs, 1 tab