Published 1985 | Version v1
Book Metadata-only

ATHENA: A two-fluid code for CANDU LOCA analysis

Creators

  • 1. Atomic Energy of Canada Ltd., Whiteshell Nuclear Research Establishment, Pinawa, Manitoba R0E 1A0

Description

ATHENA is an advanced thermalhydraulic computer code for analysis of postulated loss-of-accident (LOCA) scenarios and transient faults in CANDU nuclear reactors. In this paper, the two-fluid hydrodynamic model used in ATHENA is presented in detail. The semi-implicit numerical solution scheme employed is described and the efficiency of the method is demonstrated using examples. Comparisons are given between the predictions of ATHENA and the results of integral and separate effects tests designed to investigate phenomena important in LOCAs in CANDU and other reactor systems

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (USA)
ISBN
0-89448-122-3
Imprint Title
Proceedings of third international topical meeting on reactor thermal hydraulics
Journal Page Range
p. 7.E1-7.E14.

Conference

Title
3. international meeting on reactor thermal hydraulics.
Dates
15-18 Oct 1985.
Place
Newport, RI (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
18066010
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
A CODES; ALGORITHMS; BOILING; BUILDINGS; CANDU TYPE REACTORS; EFFICIENCY; ERRORS; FINITE DIFFERENCE METHOD; FORCED CONVECTION; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; NUMERICAL SOLUTION; PIPES; R CODES; REACTOR CHANNELS; REACTOR SAFETY; THERMODYNAMICS; TWO-PHASE FLOW; VAPOR CONDENSATION
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONVECTION; ENERGY TRANSFER; FLUID FLOW; HEAVY WATER MODERATED REACTORS; ITERATIVE METHODS; PHASE TRANSFORMATIONS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS