Published December 1980 | Version v1
Report Restricted

The effect of hot spots upon swelling of Zircaloy cladding as modelled by the code CANSWEL-2

  • 1. UKAEA Springfields Nuclear Power Development Labs.

Description

The code CANSWEL-2 models cladding creep deformation under conditions relevant to a loss-of-coolant accident (LOCA) in a pressurised-water reactor (PWR). It can treat azimuthal non-uniformities in cladding thickness and temperature, and model the mechanical restraint imposed by the nearest neighbouring rods, including situations where cladding is forced into non-circular shapes. The physical and mechanical models used in the code are presented. Applications of the code are described, both as a stand-alone version and as part of the PWR LOCA code MABEL-2. Comparison with a limited number of relevant out-of-reactor creep strain experiments has generally shown encouraging agreement with the data. (author)

Availability note (English)

MF available from INIS under the Report Number.

Files

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Additional details

Publishing Information

Imprint Pagination
22 p.
Report number
ND-R--529(S)

Conference

Title
Specialists' meeting on the safety aspects of fuel behaviour in off-normal and accident conditions.
Dates
1 - 4 Sep 1980.
Place
Espoo, Finland.

INIS

Country of Publication
United Kingdom
Country of Input or Organization
United Kingdom
INIS RN
13713616
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
C CODES; COMPUTER CODES; CREEP; DEFORMATION; FUEL CANS; FUEL ELEMENT CLUSTERS; LOSS OF COOLANT; MATHEMATICAL MODELS; PERFORMANCE; PWR TYPE REACTORS; ZIRCALOY
Descriptors DEC
ACCIDENTS; ALLOYS; FUEL ASSEMBLIES; MECHANICAL PROPERTIES; REACTOR ACCIDENTS; REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS