Comparison of GAPCON-THERMAL-3 and FRAPCON-2 fuel-performance codes to in-reactor measurement of elastic cladding deformation
Description
A revision of the GAPCON-3 computer code became part of the NRC-sponsored FRAPCON-2 code. This paper presents a comparison of both codes to in-reactor data from IFA-508, a 3-rod test rig in the Halden Reactor, Norway, which features simultaneous measurements of fuel temperature, power, axial elongation, and diametral strain. The modeling revisions included putting all regions of the fuel in contact with cladding at all time, but assigning non-linear, spatially dependent, anisotropic elastic moduli to the fuel on an incremental load step basis. The moduli are functions of the local available void within the cladding. These concepts bring demonstrable improvement to the code predictions
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01 as DE82006161.
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Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Pagination
- 17 p.
- Report number
- PNL-SA--9288
Conference
- Title
- 6. international conference on structural mechanics in reactor technology.
- Dates
- 17 - 21 Aug 1981.
- Place
- Paris (France).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14719633
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CALCULATIONS; DEFORMATION; FUEL CANS; FUEL RODS; FUEL-CLADDING INTERACTIONS; PWR TYPE REACTORS; REACTOR SAFETY
- Descriptors DEC
- FUEL ELEMENTS; REACTOR COMPONENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-810801--62.