last modified: 06-JUN-2006 | catalog | categories | new | search |

NEA-1705 IFPE/CAGR-UOX-SWELL.

IFPE/CAGR-UOX-SWELL, Fuel swelling Data Obtained from the AGR/Halden Ramp Test Programme

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1. NAME OF EXPERIMENT:  IFPE/CAGR-UOX-SWELL.
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2. COMPUTERS
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Program name Package id Status Status date
IFPE/CAGR-UOX-SWELL NEA-1705/02 Arrived 06-JUN-2006

Machines used:

No item found

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3. DESCRIPTION

An extensive study of fuel swelling in oxide fuel has been performed on fuel which has been ramp-tested in the Halden Heavy Boiling Water Reactor. The ramp-tests were performed to study the mechanisms of PCI in Advanced Gas-cooled Reactor fuel (AGR) but the initial clad deformation measurements were later supplemented by the use of Transmission Electron Microscopy (TEM) and Scanning Electron Microscopy (SEM).

The driving force for PCI arises from a combination of pellet thermal expansion and the creation of fission gas porosity during a temperature/rating transient. Fuel specimens from thirteen ramped rods and two control-reference rods have been examined using TEM and SEM. Swelling measurements have been made at four or five radial locations in the fuel. At least six full grain boundaries were used for the inter-granular study at each location and three complete trans-granular fractures employed for the intra-granular bubbles. In the latter case, the trans-granular regions were examined under very high magnifications to reveal pores as small as 20-25 nm diameter. The SEM study comprises nearly three thousand micrographs.

The microscope study was augmented by use of the ENIGMA fuel modelling code to obtain estimates of the local temperatures and conditions from which the SEM/TEM samples were obtained.
NEA-1705/02
The analysis from the 4135, 4136 and 4140 data has been incorporated. Data 4000, 4004, 4064, 4065, 4162, and 4163 have been revised. Many of the tables have been improved. The main report has been extensively modified from the earlier version.
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9. STATUS
Package ID Status date Status
NEA-1705/02 06-JUN-2006 Arrived at NEADB
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10. REFERENCES
NEA-1705/02, included references:
- R J White, R C Corcoran, and P J Barnes:
A Summary of Swelling Data Obtained from the AGR/Halden Ramp Test Programme
R&T/NG/EXT/REP/0206/02 - Issue 5 - April 2006
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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15. NAME AND ESTABLISHMENT OF AUTHORS

Data released by:
Industry Management Committee (IMC)
British Energy (BE)
British Nuclear Fuels Ltd. (BNFL)

Compilation: Rod White
  
Review: J.A. Turnbull
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16. MATERIAL AVAILABLE
NEA-1705/02
\PIADATA\ raw post-irradiation annealing data (text and Excel formats)
\ENIGMA\ input and output files from the Enigma calculations (PDF files)
\CUTTING\ PIE cutting logs (PDF files)
\INTERS-IN\ analysis of the inter-granular bubbles (ASCII format)
\INTRAS-IN\ analysis of the intra-granular bubbles (ASCII format)
\INTERS-OUT\ Processed data (ASCII format)
\INTRAS-OUT\ Processed data (ASCII format)
\REVISED DATA\ Input and Output files for the partially reanalysed cases 4000,
4004, 4064, 4065, 4162 & 4163
CalibImages.pdf Image information for the calibration images
PF-4xyz.pdf Pro Forma files of in-pile and post-irradiation annealing SEM
studies
PF-KS-x-y.pdf Pro Forma files of in-pile and post-irradiation annealing SEM
studies
report-rev-5a.pdf Main report
disc SEM-1: 4064A, 4065K, 4160E Image files (TIFF format)
disc SEM-2: 4005F, 4140A, 4159G, 4165E&F Image files (TIFF format)
disc SEM-3: 4004G, 4135E, 4163E, KS13 - KS16 (incl) Image files (TIFF format)
disc SEM-4: 4000C, KS1 - KS8 (incl) and Calibrations Image files (TIFF format)
disc SEM-5: 4136E, 4162E, KS9-KS12(incl) and KS17-KS20 (incl) (TIFF format)
ReadmeR1.txt Readme file
Swelling-SummaryR1.pdf Swelling summary
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: fission gas, fuels, pellet clad interaction (pci), power ramp, swelling.