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| Program name | Package id | Status | Status date |
|---|---|---|---|
| IFPE/IFA-535.5&6 | NEA-1548/03 | Arrived | 16-JAN-2023 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1548/03 | Many Computers |
In order to investigate the effect of fuel rod pressurization on fission gas release (FGR) two power ramp tests were performed with two pairs of re-instrumented high burnup fuel rods in the Halden Boiling Water Reactor. The fuel rods identified with the numbers 809, 810, 811 and 812 were base irradiated in the upper cluster of the two-cluster test assembly IFA-409 from May 1973 to June 1985 up to the average burnup level of 43.4 MWd/kgUO2. The neutron flux was monitored with vanadium neutron detectors located at different axial and radial positions in the assembly, but other parameters were not measured in this IFA (Instrumented Fuel Assembly). After the base irradiation the fuel rods were equipped with pressure transducers and clad elongation sensors in order to monitor the rod internal gas pressure and the mechanical behaviour during a slow and a fast power ramp in IFA-535.5 and IFA-535.6 respectively.
The re-instrumented rods were ramp tested in IFA-535.5 (rods 809 and 810) from November 1985 to February 1986, and in IFA-535.6 (rods 811 and 812) from December 1986 to May 1987. Both rigs were loaded into separated high pressure loops simulating PWR conditions thus minimizing the risk of cladding failure due to large pressure difference. The on-line rod pressure and consequently FGR monitoring made the observation of particular phenomena related to power variation possible. Beyond the in pile pressure monitoring, post irradiation examination (PIE) was performed for rods 809 and 810 in support of calculated FGR.
Keywords: BWR reactors, burnup, experimental data, fission gas release, fission products, fuel elements, fuel pellets, fuel rods, post-irradiation examination.
