Published May 2014 | Version v1
Miscellaneous

An Experimental Study on Flow Boiling Critical Heat Flux Characteristics of Suddenly Expanded Region

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

Description

In this experiment, test section has been designed to simulate sudden flow path change due to deformation of cladding. It was tended to simulate cladding deformation that has discontinuous diameter change so coolant flow path changes suddenly. Experiments are in progress. Experiments on test section that simulate deformed flow path which contains sudden contraction and sudden expansion part have been done. Location of CHF has been varied by different condition of experiment. CHF at the outlet of test section fits well into the Macbeth's correlation and data of reference experiment, which was held on plain test section that had same diameter with inlet diameter of deformed test section. CHF at sudden expansion part was in churn flow regime and CHF was very low compared to expectation. It is discussed that liquid film separation from wall or bubble accumulation by backflow might be the reason of this result. For future work, experiments for two additional blockage ratio conditions will be carried out. Also, discussion and model development for deformed channel with sudden expand flow path will be held on

Part of:
Proceedings of the KNS 2014 spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2014 spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[4 p.]

Conference

Title
2014 spring meeting of the KNS
Dates
28-30 May 2014
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
46050484
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BOILING; BUBBLES; CLADDING; CORRELATIONS; CRITICAL HEAT FLUX; FLOW BLOCKAGE; HEAT TRANSFER; REACTOR ACCIDENTS; SAFETY
Descriptors DEC
ACCIDENTS; DEPOSITION; ENERGY TRANSFER; HEAT FLUX; PHASE TRANSFORMATIONS; SURFACE COATING

Optional Information

Notes
4 refs, 5 figs, 2 tabs