Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
NEA-1705 IFPE/CAGR-UOX-SWELL.
last modified: 06-JUN-2006 | catalog | 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:

Package ID Orig. computer Test computer
NEA-1705/02 Many Computers
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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.

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 Masterfiled restricted
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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 specified programming language
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15. AUTHORS

Industry Management Committee(IMC)

British Energy (BE)

British Nuclear Fuels Ltd.(BNFL)

United Kingdom

 

Preparation: Rod White

 

Review: J.A. Turnbull

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16. MATERIAL AVAILABLE
NEA-1705/02
analysis\inters-in\   Analysis of the inter-granular
analysis\inters-out\ Processed data (ASCII)
analysis\intras-in\   Analysis of the intra-granular bubbles (ASCII)
analysis\intras-out\ Processed data (ASCII)
cutting\              PIE cutting logs (PDF files)
enigma\            input and output files from the Enigma calculations (in PDF)
piadata\           raw post-irradiation annealing data (text and Excel files)
reports\           PDF files
SEM-1\             4064A, 4065K, 4160E Image files (TIFF format)
SEM-2\             4005F, 4140A, 4159G, 4165E&F Image files (TIFF format)
SEM-3\             4004G, 4135E, 4163E, KS13 to KS16 Image files (TIFF format)
SEM-4\             4000C, KS1 to KS8 and Calibrations Image files (TIFF format)
SEM-5\             4136E, 4162E, KS9 to KS12 and KS17 to KS20 (TIFF format)
ReadmeR1.txt       Readme file
Swelling-SummaryR1.pdf Dataset of porosity and swelling measured from in-pile
ramped and out-of-pile annealed irradiated UO2
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

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