Published 1983 | Version v1
Book Metadata-only

A simple stability criterion for CANDU figure-of-eight flow oscillations

Creators

  • 1. Atomic Energy of Canada, Ltd., CANDU Operations, Sheridan Park Res. Community, Mississauga, Ontario

Description

Potential flow oscillations in CANDU reactor primary heat transport system are analyzed in terms of a simple, linearized model. A simple, algebraic stability criterion is obtained. The model predictions are found to be in good agreement with those of thermohydraulic codes for high pressure natural circulation conditions. For normal operating conditions the criterion predicts the correct trend but overlooks important stabilizing effects. The model clarifies the instability mechanism; namely the response of enthalpy and, hence, pressure in the boiling region to flow change

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
LaGrange Park, IL (USA)
ISBN
0-919784-02-X
Imprint Title
Proceedings of the international conference on numerical methods in nuclear engineering. Volume 1
Journal Page Range
p. 155-175.

Conference

Title
International conference on numerical methods in nuclear engineering.
Dates
6-9 Sep 1983.
Place
Montreal (Canada).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17051818
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BOILING; CANDU TYPE REACTORS; COMPUTER CODES; ENTHALPY; FLOW MODELS; HEAT TRANSFER; HYDRAULICS; INSTABILITY; NATURAL CONVECTION; OSCILLATIONS; PRESSURE DEPENDENCE; PRIMARY COOLANT CIRCUITS; STABILITY; THERMODYNAMICS
Descriptors DEC
CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; HEAVY WATER MODERATED REACTORS; MATHEMATICAL MODELS; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES