Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
NEA-1548 IFPE/IFA-535.5&6.
last modified: 16-JAN-2023 | catalog | new | search |

NEA-1548 IFPE/IFA-535.5&6.

IFPE/IFA-535.5&6, Fission Gas Release, Power Ramps, High Burnup Fuel

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1. NAME OF EXPERIMENT

IFPE/IFA-535.5&6

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2. COMPUTERS

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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
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3. DESCRIPTION

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.

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9. STATUS
Package ID Status date Status
NEA-1548/03 16-JAN-2023 Masterfiled restricted
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10. REFERENCES
NEA-1548/03, included references:
- V.Tosi: The Effect of Pressurisation on Fission Gas Release in High Burn-Up
BWR-Type Fuel Rods (IFA-535.5 - 6), HWR-198 (April 1987)
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. AUTHORS

OECD Halden Reactor Project

Institutt for Energiteknikk

P.O. Box 173

N-1751 HALDEN

Norway

 

Compilation: Cs. Gyori

Review: J.A. Turnbull

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16. MATERIAL AVAILABLE
NEA-1548/03
300HRS\   History files for the first 300 hrs of the ramp tests
COOLANT\ Condensed history of the coolant parameters measured during the ramp
tests
HISTORY\ Condensed history files of each fuel rod for both the base irradiation

period and the ramp test
PLOT\     Postscript format of the figures referred to in the summary file
535.pdf   Summary report
READ.ME   Readme file
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: BWR reactors, burnup, experimental data, fission gas release, fission products, fuel elements, fuel pellets, fuel rods, post-irradiation examination.