Published March 1992 | Version v1
Journal article

Evaluation of direct vessel injection design with pressurized thermal shock analysis

  • 1. Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)

Description

The purpose of this paper is to evaluate the direct vessel injection design from a pressurized thermal shock(PTS) viewpoint for the Combustion Engineering System 80+. A break of the main steam line from zero power and a 0.05 ft2 small break loss-of-coolant accident(LOCA) from full power were selected as the potential PTS events. In order to investigate the stratification effects in the reactor downcomer region, the fluid mixing analysis was performed using the COMMIX-IB code for steam line break and using the REMIX code for 0.05 ft2 small break LOCA. The stress distributions within the reactor vessel walls experiencing the pressure and the temperature transients were calculated using the OCA-P code for both events. The results of the analysis showed that a small break LOCA without decay heat presented the greatest challenge to the vessel, however, there is no crack initiation through end-of-life of the vessel with consideration of decay heat. (Author)

Additional details

Publishing Information

Journal Title
Journal of the Korean Nuclear Society
Journal Volume
24
Journal Issue
1
Journal Page Range
p. 86-97.
ISSN
0372-7327
CODEN
WJHKAW

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
24036009
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
AFTER-HEAT; COMPUTER CODES; CRACKS; DESIGN; INJECTION; LOSS OF COOLANT; PRESSURE VESSELS; REACTOR VESSELS; STEAM LINES; STRATIFICATION; THERMAL SHOCK
Descriptors DEC
ACCIDENTS; CONTAINERS; INTAKE; PIPELINES; REACTOR ACCIDENTS