Published October 2003 | Version v1
Miscellaneous

A study on the natural circulation flow through an annular gap between the reactor vessel and the insulation under external vessel cooling

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

Description

The behaviors of the boiling-induced two-phase natural circulation flow in the insulation gap were observed using an 1/21.6 scaled experimental facility to simulate the APR1400 reactor and insulation system. The liquid mass flow rates driven by natural circulation loop were measured by varying the wall heat flux, upper exit slot area and configuration. Simple loop analysis has also been performed and compared with the experimental data on the natural circulation flow rates. By the flow observation, the intensive back flow through the water inlet was generated periodically under the conditions of high heat flux and small area of the upper exit slot. Especially, when there was no steam vented slot on the upper part of water level, the periodical processes of accumulated steam venting and fresh water incoming were observed. The natural circulation mass flow rate increased as the heat flux, coolant temperature, and outlet area increased. The heat flux and coolant temperature had a larger effect on the natural circulation flow than the outlet area. The simple loop analytical results had 70% average error bound compared with experimental ones

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[CD-ROM]
Journal Page Range
[14 p.]

Conference

Title
2003 spring meeting of the KNS
Dates
29-30 May 2003
Place
Gyeongju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
35063941
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
COOLING; EXPERIMENTAL DATA; FLOW RATE; HEAT FLUX; NATURAL CONVECTION; PWR TYPE REACTORS; REACTOR VESSELS; TWO-PHASE FLOW
Descriptors DEC
CONTAINERS; CONVECTION; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HEAT TRANSFER; INFORMATION; MASS TRANSFER; NUMERICAL DATA; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
12 refs, 7 figs, 1 tab