Published 2003 | Version v1
Miscellaneous

Analysis on coolant flow in the reactor cavity under external reactor vessel cooling

  • 1. KAERI, Taejon (Korea, Republic of)

Description

As part of a study on thermal hydraulic behavior in a reactor cavity under external reactor vessel cooling in the APR 1400, preliminary analyses of the steady state for future large scale experiments using the air injection method and for the actual plant of the APR 1400 have been performed to investigate the coolant circulation mass flow rate between the reactor vessel and the insulation material using the RELAP5/MOD3 computer code. The RELAP5/MOD3 results of the preliminary analysis for the large-scale air injection experiment have shown that the coolant circulation mass flow rate of the air injection case is four times higher than that of the same heat flux boundary condition case, because of the inlet velocity vector of the air, steam condensation, and the density difference between the air and the steam. Increases in the coolant inlet, upper coolant outlet, and lower coolant outlet areas lead to an increase in the coolant circulation mass flow rate. As the lower coolant outlet moves to a lower position, the coolant circulation mass flow rate increases but the increasing rate is gradual. In the preliminary analysis of the APR 1400, the change of the lower coolant outlet to a lower position affects the coolant circulation mass flow rate, but the variation trend is not the same as the air injection experimental case

Part of:
Proceedings of the tenth international topical meeting on nuclear reactor thermal hydraulics

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Seoul (Korea, Republic of)
Imprint Title
Proceedings of the tenth international topical meeting on nuclear reactor thermal hydraulics
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[13 p.]

Conference

Title
NURETH-10
Dates
5-11 Oct 2003
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
36067261
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COOLING; FLOW RATE; HEAT FLUX; INJECTION; PWR TYPE REACTORS; R CODES; REACTOR VESSELS; THERMAL HYDRAULICS
Descriptors DEC
COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; INTAKE; MECHANICS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
11 refs, 12 figs, 4 tabs