DIANA: A multi-phase, multi-component hydrodynamic model for the analysis of severe accidents in heavy water reactors with multiple-tube assemblies

Conference · Tue Mar 01 00:00:00 EST 1994

OSTI ID:10129583

Tentner, A M

A detailed hydrodynamic fuel relocation model has been developed for the analysis of severe accidents in Heavy Water Reactors with multiple-tube Assemblies. This model describes the Fuel Disruption and Relocation inside a nuclear fuel assembly and is designated by the acronym DIANA. DIANA solves the transient hydrodynamic equations for all the moving materials in the core and treats all the relevant flow regimes. The numerical solution techniques and some of the physical models included in DIANA have been developed taking advantage of the extensive experience accumulated in the development and validation of the LEVITATE (1) fuel relocation model of SAS4A [2, 3]. The model is designed to handle the fuel and cladding relocation in both voided and partially voided channels. It is able to treat a wide range of thermal/ hydraulic/neutronic conditions and the presence of various flow regimes at different axial locations within the same hydrodynamic channel.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10129583
• Report Number(s): ANL/RA/CP-79958; CONF-940402-6; ON: DE94007627; TRN: 94:008454
• Resource Relation: Conference: International topical meeting on the safety of advanced reactors,Pittsburgh, PA (United States),18-20 Apr 1994; Other Information: PBD: [1994]
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
HEAVY WATER COOLED REACTORS
MELTDOWN
CORIUM
HYDRODYNAMIC MODEL
REACTOR CHANNELS
FLUID FLOW
FUEL ELEMENTS
REACTOR SAFETY
D CODES
L CODES
S CODES
HEAT TRANSFER
HYDRAULICS
220900
210400
990200
POWER REACTORS
NONBREEDING
OTHERWISE MODERATED OR UNMODERATED
MATHEMATICS AND COMPUTERS