Published January 2013 | Version v1
Report Restricted

Interfacial area transport model development for the two-phase flow in research reactor fuel element

Creators

  • 1. Kyoto University, Research Reactor Institute, Kumatori, Osaka (Japan)
  • 2. School of Nuclear Engineering, Purdue University, West Lafayette, IN (United States)

Description

no abstract available

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Part of:
Proceedings of the 47th KURRI scientific meeting

Additional details

Publishing Information

Imprint Title
Proceedings of the 47th KURRI scientific meeting
Imprint Pagination
275 p.
Journal Page Range
p. 166-171
Report number
KURRI-KR--176

Conference

Title
47. KURRI scientific meeting
Dates
29-30 Jan 2013
Place
Kumatori, Osaka (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
47083223
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
No Abstract, Conference
Descriptors DEI
BOILING; BUBBLES; COMPUTERIZED SIMULATION; DIFFUSION; FUEL ELEMENTS; INTERFACES; NEUTRON RADIOGRAPHY; PIPES; POWER TRANSMISSION; REACTOR CORES; REACTOR SAFETY; RESEARCH REACTORS; TRANSPORT THEORY; TURBULENT FLOW; TWO-PHASE FLOW
Descriptors DEC
FLUID FLOW; INDUSTRIAL RADIOGRAPHY; MATERIALS TESTING; NONDESTRUCTIVE TESTING; PHASE TRANSFORMATIONS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SIMULATION; TESTING; TUBES

Optional Information

Notes
5 refs., 2 figs.