NEA-1546 IFPE/IFA-429.
IFPE/IFA-429, Fission Gas Release, Thermal Behaviour U02 Fuel, Halden Reactor
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/IFA-429 | NEA-1546/01 | Arrived | 12-NOV-1997 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1546/01 | Many Computers |
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3. DESCRIPTION
PWR type fuel rods assembled in three axially separated clusters of six rods were irradiated in the Halden Boiling Water Reactor as IFA-429 from June 1975 to September 1990. The eighteen-rod assembly had been designed to investigate gas absorption, fission gas release (FGR) and thermal behaviour of UO2 fuel during both steady state operation period and rapid power transients. In order to achieve the objectives, two rods were instrumented with fuel centre line thermocouples (TFs)and nine rods were instrumented with null-balance gas pressure transducers (PFs) monitoring rod internal gas pressure. The assembly was instrumented with nine vanadium neutron detectors, one cobalt detector, inlet and outlet coolant thermocouples and an inlet coolant flow turbine as well.
This database contains the measured temperature history for one of the middle cluster rods up to the burnup level of 53 MWd/kgUO2 and the measured internal pressure data for three upper and three lower cluster steady-state irradiated fuel rods subjected to rapid power transients. Rationalized power histories are also presented for all the seven rods.
In order to study FGR two series of power ramps were induced in August 1985 and in March 1988 by movable neutron absorbing shield surrounding the fuel rod clusters. Manually initiated gas pressure measurements were performed during the testing sequence. The FGR and the gas diffusion coefficients calculated on the basis of the measured rod internal pressure data are tabulated as well. Due to slightly different design characteristics of the six investigated fuel rods, the comparison of FGR data at three different fuel densities (91% TD, 93% TD and 95% TD), at two different grain sizes (6 um and 17 um) and at two different fuel-cladding gap sizes (200 um and 360 um) are possible.
As the null-balance pressure transducers were not part of the automatic data acquisition system the rod internal gas pressure data set is limited. Only the pressure data measured at zero power during the base irradiation period, and the average value of the pressures measured during the two series of rapid power transients are tabulated. Calculated fission gas release (FGR) data are also presented.
PWR type fuel rods assembled in three axially separated clusters of six rods were irradiated in the Halden Boiling Water Reactor as IFA-429 from June 1975 to September 1990. The eighteen-rod assembly had been designed to investigate gas absorption, fission gas release (FGR) and thermal behaviour of UO2 fuel during both steady state operation period and rapid power transients. In order to achieve the objectives, two rods were instrumented with fuel centre line thermocouples (TFs)and nine rods were instrumented with null-balance gas pressure transducers (PFs) monitoring rod internal gas pressure. The assembly was instrumented with nine vanadium neutron detectors, one cobalt detector, inlet and outlet coolant thermocouples and an inlet coolant flow turbine as well.
This database contains the measured temperature history for one of the middle cluster rods up to the burnup level of 53 MWd/kgUO2 and the measured internal pressure data for three upper and three lower cluster steady-state irradiated fuel rods subjected to rapid power transients. Rationalized power histories are also presented for all the seven rods.
In order to study FGR two series of power ramps were induced in August 1985 and in March 1988 by movable neutron absorbing shield surrounding the fuel rod clusters. Manually initiated gas pressure measurements were performed during the testing sequence. The FGR and the gas diffusion coefficients calculated on the basis of the measured rod internal pressure data are tabulated as well. Due to slightly different design characteristics of the six investigated fuel rods, the comparison of FGR data at three different fuel densities (91% TD, 93% TD and 95% TD), at two different grain sizes (6 um and 17 um) and at two different fuel-cladding gap sizes (200 um and 360 um) are possible.
As the null-balance pressure transducers were not part of the automatic data acquisition system the rod internal gas pressure data set is limited. Only the pressure data measured at zero power during the base irradiation period, and the average value of the pressures measured during the two series of rapid power transients are tabulated. Calculated fission gas release (FGR) data are also presented.
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4. METHOD OF SOLUTION
As the measured parameters were recorded in every 15th minute of the fifteen-year irradiation time, the huge original test fuel data base is not applicable for model validation without any rationalization. Hence the data were reduced on the basis of power history condensation performed for each rod. For the condensed histories new irradiation time is calculated on the basis of the burnup. However, for the investigation of some phenomena the 15 min. data acquisition frequency is required. Therefore some data from selected irradiation periods are presented without any condensation.
As the measured parameters were recorded in every 15th minute of the fifteen-year irradiation time, the huge original test fuel data base is not applicable for model validation without any rationalization. Hence the data were reduced on the basis of power history condensation performed for each rod. For the condensed histories new irradiation time is calculated on the basis of the burnup. However, for the investigation of some phenomena the 15 min. data acquisition frequency is required. Therefore some data from selected irradiation periods are presented without any condensation.
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10. REFERENCES
- W.H. Jens and P.A. Lottes:
Analysis of Heat Transfer, Burn-out, Pressure Drop and Density
Data for High Pressure Water
ANL-4627 (1951)
- W.H. Jens and P.A. Lottes:
Analysis of Heat Transfer, Burn-out, Pressure Drop and Density
Data for High Pressure Water
ANL-4627 (1951)
NEA-1546/01, included references:
M.E.Cunningham,K.Svanholm:Fission Gas Release from PWR-Type Rods in IFA-429 during Rapid and
Short Power Increases, HWR-159 (March 1986)
M.R.Smith, P.M.Crosby,J.M.Aasgaard,Y.Minagawa:
Fission Gas Release during a Second Series of Rapid Power Increases
on IFA-429 Rods at 40 GWD/TUO2, HWR-237 (April 1988)
H.Devold,H.Wallin:
PIE Results from the High Burnup Rods CD/CH (IFA-429) and Comparison with
with In-Pile Data, HWR-409 (October 1994)
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NEA-1546/01
miscellaneous mag tapeREAD.ME Information file MISTPmiscellaneous mag tape429.SUM Summary about the experiment MISTP
test-case data mag tapeRODAB.DAT History file for Rod AB DATTP
test-case data mag tapeRODAD.DAT History file for Rod AD DATTP
test-case data mag tapeRODAH.DAT History file for Rod AH DATTP
test-case data mag tapeRODBC.DAT History file for Rod BC DATTP
test-case data mag tapeRODCB.DAT History file for Rod CB DATTP
test-case data mag tapeRODCD.DAT History file for Rod CD DATTP
test-case data mag tapeRODCH.DAT History file for Rod CH DATTP
test-case data mag tapeTFBC.27 Tab.th.couple readings at27kW/m rodDATTP
test-case data mag tapeTFBC.BU Tab.th.couple read. 4 burnup levelsDATTP
test-case data mag tapePF429.DAT Press.data of 6 rods (zero power)DATTP
test-case data mag tapePFBOL.DAT Press.data of 6 rods at BOL DATTP
test-case data mag tapeFGR.DAT Tab.data of Fission Gas Release DATTP
test-case output mag tapeFIG1.PS Figure of summary file(Postscript) OUTTP
test-case output mag tapeFIG23.PS Figure of summary file(Postscript)OUTTP
test-case output mag tapeFIG4.PS Figure of summary file(Postscript) OUTTP
test-case output mag tapeFIG5.PS Figure of summary file(Postscript) OUTTP
test-case output mag tapeFIG6.PS Figure of summary file(Postscript) OUTTP
test-case output mag tapeFIG7.PS Figure of summary file(Postscript) OUTTP
test-case output mag tapeFIG8.PS Figure of summary file(Postscript) OUTTP
Keywords: BWR reactors, burnup, experimental data, fission gas release, fission products, fuel elements, fuel pellets, fuel rods, pwr reactors, thermal conductivity.