Published September 1995 | Version v1
Report Metadata-only

Two-phase flow stability structure in a natural circulation system

Creators

  • 1. Nuclear Engineering Laboratory Zurich (Switzerland)

Description

The present study reports a numerical analysis of two-phase flow stability structures in a natural circulation system with two parallel, heated channels. The numerical model is derived, based on the Galerkin moving nodal method. This analysis is related to some design options applicable to integral heating reactors with a slightly-boiling operation mode, and is also of general interest to similar facilities. The options include: (1) Symmetric heating and throttling; (2) Asymmetric heating and symmetric throttling; (3) Asymmetric heating and throttling. The oscillation modes for these variants are discussed. Comparisons with the data from the INET two-phase flow stability experiment have qualitatively validated the present analysis

Additional details

Publishing Information

Imprint Title
Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Volume 2, Sessions 6-11
Imprint Pagination
795 p.
Journal Page Range
p. 888-910.
Report number
NUREG/CP--0142-Vol.2

Conference

Title
7. international meeting on nuclear reactor thermal hydraulics.
Dates
10-15 Sep 1995.
Place
Saratoga, NY (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27019684
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BWR TYPE REACTORS; DIAGRAMS; HYDRAULICS; MATHEMATICAL MODELS; NATURAL CONVECTION; NUMERICAL ANALYSIS; NUMERICAL DATA; REACTOR CORES; REACTOR SAFETY; STABILITY; TWO-PHASE FLOW; VORONEZH AST-500 REACTOR
Descriptors DEC
CONVECTION; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HEAT TRANSFER; INFORMATION; MATHEMATICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-950904--Vol.2.