Published 2011 | Version v1
Miscellaneous

DNB prediction using local void distribution in high quality flow

  • 1. Nuclear Fuel Industries, Ltd., Osaka (Japan)
  • 2. Univ. of Osaka, Osaka (Japan)

Description

A coupled code between a sub-channel analysis code and a computational multi-fluid dynamics code was developed for predicting departure from nucleate boiling (DNB). Local void fraction near the wall was used to define the onset of DNB. The local void fraction distribution in a sub-channel was determined by a bubble diffusion equation. To cover the flow regime at the high quality condition, a new source term was introduced. The present method was applied to the analysis of DNB test data including high quality condition. The result showed remarkable improvement of predictability by introducing the new source term. (author)

Part of:
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-05-6
Imprint Title
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)
Imprint Pagination
766 Megabytes
Journal Page Range
[12 p.]

Conference

Title
14. International Topical Meeting on Nuclear Reactor Thermalhydraulics
Acronym
NURETH-14
Dates
25-30 Sep 2011
Place
Toronto, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
47071382
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BUBBLES; COMPUTERIZED SIMULATION; DEPARTURE NUCLEATE BOILING; DIFFUSION EQUATIONS; FLUID MECHANICS; REACTOR CHANNELS; VOID FRACTION
Descriptors DEC
BOILING; DIFFERENTIAL EQUATIONS; EQUATIONS; MECHANICS; NUCLEATE BOILING; PARTIAL DIFFERENTIAL EQUATIONS; PHASE TRANSFORMATIONS; REACTOR COMPONENTS; SIMULATION

Optional Information

Notes
Paper NURETH14-171, 12 refs., 1 tab., 10 figs.