Published October 2007 | Version v1
Miscellaneous

Critical angle for the inclined pipe to distinguish horizontal and vertical character

  • 1. School of Mechanical and Control Engineering, Seoul (Korea, Republic of)
  • 2. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

Description

Safety analysis codes of nuclear power plant have equipped the flow regime map to provide the proper constitutive relations corresponding to the flow regime. Traditionally, the flow regimes for the vertical flow and horizontal flow have been investigated intensively and we have very reliable map and criteria to be useful for the computer code. However, for the inclined pipe, we have lack of experimental works and transition criteria to be used. Actually, in the pressurized heavy water nuclear reactor like CANDU, certain part of pipe line has inclination angle. At this moment the safety code such as RELAP-CANDU has no flow regime map for the inclined pipe, Engineering judgment intuitively suggested to take the reference angle and horizontal flow regime map for the inclined pipe with the lower angle than the reference and vertical flow regime map for the larger angle than the reference angle. Also, as the reference angle it has been suggested that 45 degree may compromise the difference of two dominant flow regime. However, it has no physical bases. Also, it casted fundamental questions on the drift flux model and the effect of gravity on the instability of two-phase flow. Therefore, the present study is designed to find the reference angle to distinguish the horizontal flow regime map and vertical flow regime map. The study was made based on the experimental way with the special intelligent identifier to remove any chance of human subjective perception

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

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

Conference

Title
2007 autumn meeting of the KNS
Dates
25-26 Oct 2007
Place
Pyongchang (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
39077848
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; NUCLEAR POWER PLANTS; PIPES; R CODES; SAFETY ANALYSIS; TWO-PHASE FLOW
Descriptors DEC
COMPUTER CODES; FLUID FLOW; HEAVY WATER MODERATED REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; TUBES

Optional Information

Notes
2 refs, 4 figs