Published 2005 | Version v1
Conference paper

Development of multidimensional mechanistic models of two-phase flow for the NPHASE CFD code

  • 1. Dept. of Mechanical, Aerospace and Nuclear Engineering, and Center for Multiphase Research, Rensselaer Polytechnic Institute, Troy, NY 12180 (United States)

Description

Full text of publication follows: This paper is concerned with the development of advanced multidimensional multiphase flow and heat transfer modeling and CFD simulation capabilities for application in nuclear reactor thermal-hydraulics. The accuracy of CFD predictions depends on the quality of closure models for local two phase flow phenomena under consideration. The majority of existing CFD codes use simplified closure laws, actually applicable only to dispersed bubbly/particle flows, where the interfacial interactions are limited to the drag and, possibly, virtual mass forces. In the present work, the recently developed models for slug and annular flows, as well as new models of subcooled boiling and CHF have been implemented in the NPHASE code and fully coupled with an advanced numerical solution algorithm. As a result of this, several generic closure laws, both local and mixed local/global (defined by specific mathematical operators and formulae) are available to model major flow regimes encountered in nuclear reactor systems. A fully coupled multidimensional multi-field mass/momentum flow solver that has been implemented in the NPHASE code allows for a tight coupling between the numeric and individual physical models of two-phase flow. Selected results of testing and validating the new models will be shown in the full paper. Specifically, the results of simulations will be discussed of two-phase flows for various flow regimes and nuclear reactor operating conditions. Furthermore, the final goal of the effort is to have the models of individual flow regimes linked together into a single scalable multidimensional model of a heated channel applicable over a wide range of conditions of interest in reactor thermal-hydraulic and safety analysis. (authors)

Availability note (English)

Available in abstract form only, full text entered in this record
Part of:
11. international topical meeting on nuclear reactor thermal-hydraulics (NURETH-11)

Additional details

Publishing Information

Imprint Pagination
1 p.
Report number
INIS-FR--3515

Conference

Title
11. international topical meeting on nuclear reactor thermal hydraulics (Nureth 11)
Dates
2-6 Oct 2005
Place
Avignon (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
36047845
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; FLOW MODELS; HEAT TRANSFER; N CODES; NUMERICAL SOLUTION; SUBCOOLED BOILING; THERMAL HYDRAULICS; TWO-PHASE FLOW; VALIDATION
Descriptors DEC
BOILING; COMPUTER CODES; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MATHEMATICAL MODELS; MATHEMATICAL SOLUTIONS; MECHANICS; PHASE TRANSFORMATIONS; SIMULATION; TESTING

Optional Information