NEA-1634 IFPE/RISOE-I
IFPE/RISOE-1, Fission gas release from high-burnup water reactor fuel
NAME OF EXPERIMENT, COMPUTER, DESCRIPTION, SOLUTION, RESTRICTIONS, CPU, FEATURES, AUXILIARIES, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| IFPE/RISOE-I | NEA-1634/01 | Arrived | 09-MAR-2005 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1634/01 | Many Computers |
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3. DESCRIPTION
The objective of the Risoe Fission Gas Project was to provide experimental data on fission gas release from high-burnup water reactor fuel. The data were obtained with Zircaloy clad U02 pellet fuel, irradiated in the Halden Reactor to a burnup of 32,000 MWD/Tu (assembly average). Most of the 12 fuel pins used in the Project were submitted to short-term re-irradiations at increased power levels, so-called "bump testing", in the DR 3 test reactor at Risoe. Unbumped and bump-tested fuel pins were examined in the Risoe hot cells, with some additional examination of special samples at the European Institute for Transuranium Elements in Karlsruhe (F.R. Germany).
The fuel pins used in the Project were base irradiated in the Halden boiling heavy-water reactor (Norway) in the Danish fuel assembly IFA 148. The pin average heat load was generally decreasing from 320 to 180 W/cm, with a short period at 390 W/cm in the beginning of the irradiation period. The assembly average burnup was 31,700 MWD/tU (peak pellet 43,700 MWD/tU). The bump testing was performed in the DR 3 Reactor at Risoe at a coolant pressure of 70 atm. 11 tests were carried out with 9 fuel pins; rebumping of two of the pins was feasible because the fission gas content could be assessed non-destructively by the Risoe plenum spectrometry technique. Similarly, the fission gas content prior to bumping was measured for all pins. The test covered a range of peak pellet bump terminal levels (BTL) of 301-434 W/cm and 24 hrs. hold time (HT).
The objective of the Risoe Fission Gas Project was to provide experimental data on fission gas release from high-burnup water reactor fuel. The data were obtained with Zircaloy clad U02 pellet fuel, irradiated in the Halden Reactor to a burnup of 32,000 MWD/Tu (assembly average). Most of the 12 fuel pins used in the Project were submitted to short-term re-irradiations at increased power levels, so-called "bump testing", in the DR 3 test reactor at Risoe. Unbumped and bump-tested fuel pins were examined in the Risoe hot cells, with some additional examination of special samples at the European Institute for Transuranium Elements in Karlsruhe (F.R. Germany).
The fuel pins used in the Project were base irradiated in the Halden boiling heavy-water reactor (Norway) in the Danish fuel assembly IFA 148. The pin average heat load was generally decreasing from 320 to 180 W/cm, with a short period at 390 W/cm in the beginning of the irradiation period. The assembly average burnup was 31,700 MWD/tU (peak pellet 43,700 MWD/tU). The bump testing was performed in the DR 3 Reactor at Risoe at a coolant pressure of 70 atm. 11 tests were carried out with 9 fuel pins; rebumping of two of the pins was feasible because the fission gas content could be assessed non-destructively by the Risoe plenum spectrometry technique. Similarly, the fission gas content prior to bumping was measured for all pins. The test covered a range of peak pellet bump terminal levels (BTL) of 301-434 W/cm and 24 hrs. hold time (HT).
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NEA-1634/01, included references:
- Per Knudsen:Pre-Irradiation Data on IFA 148 Fuel Pins
RISOE-FGP-R1 (May 1980)
- C. Bagger, B.S. Johansen and P. Knudsen:
Non-Destructive Examination of IFA 148
RISOE-FGP-R3 (October 1980)
- M. Mogensen, E. Larsen, J. Funck and T.R. Strauss:
Radiochemical Burnup Determination and Isotope Analysis of
Four IFA 148 Samples
RISOE-FGP-R7 (June 1981)
- C. Bagger and P.B. Olesen:
Diametral Micro Gamma Scanning of Unbumped and Bump-Tested
IFA 148 Samples
RISOE-FGP-R8 (November 1981)
- M. Mogensen and C. Mikkelsen:
Retained Gas Measurements on IFA 148 Samples
RISOE-FGP-R9 (November 1981)
- H. Carlsen, K. Jensen and T.R. Strauss:
Ceramography on Archive Pellets and Samples from IFA 148
RISOE-FGP-R10 (November 1981)
- I. Misfeldt and H. Carlsen:
Quantitative Image Analysis of Samples from IFA 148
RISOE-FGP-R11 (November 1981)
- I. Misfeldt, J. Aukdal and P. Knudsen:
Halden Irradiation of IFA 148
RISOE-FGP-R12 (October 1981)
- C.T. Walker, I.L.F. Ray, M. Coquerelle and H. Blank:
Fission Gas Release and Swelling in the Fuel Pins M1-3 and F9-3
RISOE-FGP-R13 (January 1982)
- P. Knudsen, I. Misfeldt, C. Bagger and K. Hansen:
Irradiation Data for Bump Tests 1-11
RISOE-FGP-R14Rev. (June 1983)
- C. Bagger et al.:
Non-Destructive Examination of Bump Tests 1-11
RISOE-FGP-R15 (November 1981)
- H. Carlsen et al.:
Puncturing Results and Plenum Spectrometry on IFA 148 Pins
and Bump Tests 1-11
RISOE-FGP-R16 (March 1982)
- P. Knudsen et al.:
Final Report on the Risoe Fission Gas Project
RISOE-FGP-R17rev. (June 1983)
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NEA-1634/01
R1.PDF RISOE-FGP-R1 documentR3.PDF RISOE-FGP-R3 document
R7.PDF RISOE-FGP-R7 document
R8.PDF RISOE-FGP-R8 document
R9.PDF RISOE-FGP-R9 document
R10.PDF RISOE-FGP-R10 document
R11.PDF RISOE-FGP-R11 document
R12.PDF RISOE-FGP-R12 document
R13.PDF RISOE-FGP-R13 document
R14rev.PDF RISOE-FGP-R14rev document
R15.PDF RISOE-FGP-R15 document
R16.PDF RISOE-FGP-R16 document
R17rev.PDF RISOE-FGP-R17rev document
Summary of Risoe 1 Fission Gas Project
Pre-characterization of fuel rods
PIE results for Risoe 1 Bump Tests
BT-x.A (1 to 11) Irradiation histories for 11 tests using time average
HBWR axial form factor
BT-x.B (1 to 11) Irradiation histories for each test using time dependent
HBWR axial form factor
QA report for Risoe 1 Details of how data were received and processed
BT-x.IN (1 to 11) input files for Fortran processing program (for QA only)
RISA.FOR FORTRAN processing program included for QA purposes only
Keywords: experimental data, fission gas release, fission products, fuel elements, fuel pellets, high burnup, water reactor fuel.