NEA-1493 IFPE/RISOE-III.
IFPE/RISOE-III, Fuel Performance Data from 3rd Risoe Fission Gas Release
NAME OF EXPERIMENT, COMPUTER, DESCRIPTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| IFPE/RISOEIII | NEA-1493/17 | Arrived | 19-SEP-1995 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1493/17 | Many Computers |
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3. DESCRIPTION
The Risoe National Laboratory in Denmark have carried out three irradiation programs of slow ramp and hold tests, so called 'bump tests' to investigate fission gas release and fuel microstructural changes. The third and final project which took place between 1986 and 1990 bump tested fuel re-instrumented with both pressure transducers and fuel centreline thermocouples.
The innovative technique employed for re-fabrication involved freezing the fuel rod to hold the fuel fragments in position before cutting and drilling away the centre part of the solid pellets to accommodate the new thermocouple.
The fuel used in the project was from: IFA-161 irradiated in the Halden BWR (irradiation history provided) 13 to 46 MWd/kgUO2, GE BWR fuel irradiated in Quad Cities 1 and Millstone 1 20 to 40 MWd/kgUO2 and ANF PWR fuel irradiated in Biblis A to 38 MWd/kgUO2.
The data from the project are particularly valuable because of the in-pile data on fuel temperatures and pressures as well as extensive post irradiation examination (PIE). More specifically the tests are characterized as follows:
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Test Type Burn-up BTL Fill Gas Hold Time Purpose
% FIMA kW/m hours
------------------------------------------------------------------
AN1 P 4.4 39.8 15 bar He 42 Effect of
refabrication
AN2 U 4.3 39.0 25 bar He 62 Effect of power
history and
refabrication
AN3 TP 4.4 40.7 15 bar He 42 Effect of fill
gas and
refabrication
AN4 TP 4.4 40.7 1 bar Xe 42 Effect of fill gas
AN8 U 4.3 29.8 25 bar He 4 Power history,
fuel type and low
power FGR
AN10 TP 4.4 34.4 5 bar He 40 Power history,
low power FGR
AN11 U 4.4 16.9 25 bar He 4 Low power FGR
GE2 TP 4.21 40.5 5 bar He 41 Effect of burn-up
and power history
GE4 TP 2.4 43.3 5 bar He 34 Effect of burn-up
and fuel grain
size
GE6 TP 3.71 37.9 5 bar He 140 Power history
GE7 U 4.17 35.5 3 bar He 4 Power history and
fuel type
II1 T 4.8 40.3 1 bar Xe 24 Link to 2nd project
II2 TP 2.8 42.8 5 bar He 2 Link to 2nd project
II3 TP 1.6 44.7 5 bar He 36 Burn-up, link to
project
II5 TP 5.3 40.1 5 bar He 24 Burn-up, link to
2nd project
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Note: BTL refers to Bump Terminal Level (Power)
T = fuel centreline thermocouple, P = pressure transducer
U = unopened
ANx was a test with ANF PWR fuel irradiated in Biblis A
GEx was a test with GE BWR fuel irradiated in Quad Cities 1
II1 and II5 used fuel from HBWR irradiated IFA-161
II2 and II3 used GE fuel irradiated in Millstone 1
Data sets identified as ANx stem from a test with ANF PWR fuel irradiated in Biblis A, those with GEx from a test with GE BWR fuel irradiated in Quad Cities 1 II1 and II5 from tests with HBWR fuel irradiated in Halden (IFA-161) and II2 and II3 from tests with GE BWR fuel irradiated in Millstone 1.
The Risoe National Laboratory in Denmark have carried out three irradiation programs of slow ramp and hold tests, so called 'bump tests' to investigate fission gas release and fuel microstructural changes. The third and final project which took place between 1986 and 1990 bump tested fuel re-instrumented with both pressure transducers and fuel centreline thermocouples.
The innovative technique employed for re-fabrication involved freezing the fuel rod to hold the fuel fragments in position before cutting and drilling away the centre part of the solid pellets to accommodate the new thermocouple.
The fuel used in the project was from: IFA-161 irradiated in the Halden BWR (irradiation history provided) 13 to 46 MWd/kgUO2, GE BWR fuel irradiated in Quad Cities 1 and Millstone 1 20 to 40 MWd/kgUO2 and ANF PWR fuel irradiated in Biblis A to 38 MWd/kgUO2.
The data from the project are particularly valuable because of the in-pile data on fuel temperatures and pressures as well as extensive post irradiation examination (PIE). More specifically the tests are characterized as follows:
------------------------------------------------------------------
Test Type Burn-up BTL Fill Gas Hold Time Purpose
% FIMA kW/m hours
------------------------------------------------------------------
AN1 P 4.4 39.8 15 bar He 42 Effect of
refabrication
AN2 U 4.3 39.0 25 bar He 62 Effect of power
history and
refabrication
AN3 TP 4.4 40.7 15 bar He 42 Effect of fill
gas and
refabrication
AN4 TP 4.4 40.7 1 bar Xe 42 Effect of fill gas
AN8 U 4.3 29.8 25 bar He 4 Power history,
fuel type and low
power FGR
AN10 TP 4.4 34.4 5 bar He 40 Power history,
low power FGR
AN11 U 4.4 16.9 25 bar He 4 Low power FGR
GE2 TP 4.21 40.5 5 bar He 41 Effect of burn-up
and power history
GE4 TP 2.4 43.3 5 bar He 34 Effect of burn-up
and fuel grain
size
GE6 TP 3.71 37.9 5 bar He 140 Power history
GE7 U 4.17 35.5 3 bar He 4 Power history and
fuel type
II1 T 4.8 40.3 1 bar Xe 24 Link to 2nd project
II2 TP 2.8 42.8 5 bar He 2 Link to 2nd project
II3 TP 1.6 44.7 5 bar He 36 Burn-up, link to
project
II5 TP 5.3 40.1 5 bar He 24 Burn-up, link to
2nd project
--------------------------------------------------------------------
Note: BTL refers to Bump Terminal Level (Power)
T = fuel centreline thermocouple, P = pressure transducer
U = unopened
ANx was a test with ANF PWR fuel irradiated in Biblis A
GEx was a test with GE BWR fuel irradiated in Quad Cities 1
II1 and II5 used fuel from HBWR irradiated IFA-161
II2 and II3 used GE fuel irradiated in Millstone 1
Data sets identified as ANx stem from a test with ANF PWR fuel irradiated in Biblis A, those with GEx from a test with GE BWR fuel irradiated in Quad Cities 1 II1 and II5 from tests with HBWR fuel irradiated in Halden (IFA-161) and II2 and II3 from tests with GE BWR fuel irradiated in Millstone 1.
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NEA-1493/17, included references:
- The Third Risoe Fission Gas Project Bump Test AN1 (CB9-2R)RISOE-FGP3-AN1 (September 1990)
- The Third Risoe Fission Gas Project Bump Test AN2 (CB6)
RISOE-FGP3-AN2 (September 1990)
- The Third Risoe Fission Gas Project Bump Test AN3 (CB8-2R)
RISOE-FGP3-AN3 (September 1990)
- The Third Risoe Fission Gas Project Bump Test AN4 (CB7-2R)
RISOE-FGP3-AN4 (September 1990)
- The Third Risoe Fission Gas Project Bump Test AN8 (CB10)
RISOE-FGP3-AN8 (September 1990)
- The Third Risoe Fission Gas Project Bump Test AN10 (CB13-4R)
RISOE-FGP3-AN10 (September 1990)
- The Third Risoe Fission Gas Project Bump Test AN11 (CB11)
RISOE-FGP3-AN11 (September 1990)
- The Third Risoe Fission Gas Project ANF Fuel (ANF-Data)
RISOE-FGP3-ANF,Pt.1 (September 1990)
- The Third Risoe Fission Gas Project ANF Fuel (Risoe-Data)
RISOE-FGP3-ANF,Pt.2 (September 1990)
- The Third Risoe Fission Gas Project Bump Test GE2 (ZX114-3R)
RISOE-FGP3-GE2 (September 1990)
- The Third Risoe Fission Gas Project Bump Test GE4 (XW104-3R)
RISOE-FGP3-GE4 (September 1990)
- The Third Risoe Fission Gas Project Bump Test GE6 (ZX113-4R)
RISOE-FGP3-GE6 (September 1990)
- The Third Risoe Fission Gas Project Bump Test GE7 (ZX115)
RISOE-FGP3-GE7 (September 1990)
- The Third Risoe Fission Gas Project GE Fuel (GE-Data)
RISOE-FGP3-GE, Pt.1 (April 1990)
- The Third Risoe Fission Gas Project GE Fuel (Risoe-Data)
RISOE-FGP3-GE, Pt.2 (September 1990)
- The Third Risoe Fission Gas Project Bump Test II1 (M72-2-2R)
RISOE-FGP3-II1 (September 1990)
- The Third Risoe Fission Gas Project Bump Test II2 (STR024-2R)
RISOE-FGP3-II2 (September 1990)
- The Third Risoe Fission Gas Project Bump Test II3 (STR014-3R)
RISOE-FGP3-II3 (September 1990)
- The Third Risoe Fission Gas Project Bump Test II5 (M72-2-7R)
RISOE-FGP3-II5 (September 1990)
- The Third Risoe Fission Gas Project TU Final Report (1/3)
RISOE-FGP3-TU,Pt.1 (April 1992)
- The Third Risoe Fission Gas Project TU Final Report (2/3)
RISOE-FGP3-TU,Pt.2 (April 1992)
- The Third Risoe Fission Gas Project TU Final Report (3/3)
RISOE-FGP3-TU,Pt.3 (April 1992)
- The Third Risoe Fission Gas Project Final Report: The Project
RISOE-FGP3-FINAL,Pt.1 (March 1991)
- The Third Risoe Fission Gas Project Final Report: The Methods
RISOE-FGP3-FINAL,Pt.2 (March 1991)
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NEA-1493/17
PRECHAR.*.* Precharacterization data for each testBASEHIST.*.* Base irradiation
TESTPOW.*.* Linear heat rating
TEMP.*.* For T-tests, measured fuel centreline temperatures
TFVPOW.*.* For T-tests, selected values of temperature and power
PRESS.*.* For P-tests, measured internal pressure
FGR.*.* Fission gas release
PIE.*.* PIE data for each test
EPMA.*.* Measurement of retained xenon concentration (measured by EPMA)
MGx.*.* Measurement of retained 137-Cs concentration
XRFx.*.* Measurement of retained xenon concentration (measured by X-ray)
QIAx.*.* Porosity measurements across pellet radius
MG.* Microgamma scanning profiles across pellets
XRF.* X-ray fluorescence profiles across pellets
Description of the data and readme file
Keywords: experimental data, fission gas release, fission products, fuel elements, fuel pellets, fuel rods, fuel-cladding interaction, fuel-coolant interactions, helium, xenon.