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CSNI2106 CABRI-REPNA-10 TEST.

CABRI-REPNa-10 TEST, Assessment of fuel behaviour mechanisms relevant for RIA transients

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1. NAME OR DESIGNATION:  CABRI-REPNa10 TEST
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2. COMPUTERS
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Machines used:

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3. DESCRIPTION OF TEST FACILITY

The CABRI REP Na test data provide a very consistent basis for the assessment of fuel behaviour mechanisms relevant for RIA transients. For the CABRI REP Na rods that did not fail,  valuable information on fission gas release and especially on cladding deformation have been generated in the test programme. REP Na cladding strain data have been used as a start point for deriving an admittedly simple RIA failure criterion. This is based on a maximum strain which can be tolerated by the cladding, i.e. failure can occur only when this strain level is exceeded.
- For cladding that still retains ductility, failure at high burn-up (50-60 MWd/kg) is predicted beyond a 1% (permanent) diameter strain.
- For cladding that has been embrittled due to e.g. large corrosion, spalling and hydriding, a zero ductility is assumed, i.e. the failure threshold is at onset (0%) of permanent strain.
  
The conditions under which the ductility decreases from 1% to zero are provisionally set in the paper, taking into account the evidence from the CABRI tests and from ANL laboratory tests. Based on the above, one derives that the lowest failure limit at 60 MWd/kg is ~65-70 cal/g, which applies to heavily corroded/hydrided fuel, i.e. for oxide thickness of ~80 mm and in presence of oxide spalling. For corrosion resistant fuel, i.e. for oxide thickness well below 80 mm and in absence of spalling, the failure threshold at the same burnup is ~100 cal/g.
  
This failure criterion predicts well three of the four failed REP Na tests, but not the REP Na-1 test. For this, the predicted failure threshold is 63 cal/g, whereas the reported experimental value is 30 cal/g. For CABRI unfailed rods, the predicted failure limit is very close to the enthalpy achieved during the test. When used at its higher degree of conservatism (i.e. ductility = 0), the proposed failure threshold predicts reasonably well also the failed NSRR PWR and BWR rods. In general, more data at prototypical conditions are needed in order to arrive to comprehensive, best-estimate failure predictions. The PIE data of unfailed REP Na rods show a remarkable similarity between the trend exhibited by the cladding strain and by the fission gas release. This is briefly discussed in this paper with regard to a possible FGR mechanism (i.e. it is implied that the gas may mostly be released upon cooling, when cladding constraints are reduced). In any case, it appears that FGR as such has little to do with the mechanism of failure when this occurs at low enthalpy.
  
For more detailed information visit
http://www.nea.fr/html/dbprog/cabrirepna/CABRI-REPNa.htm  and
http://www.nea.fr/html/jointproj/cabri.html
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4. DESCRIPTION OF TEST

The REPNa10 test, performed on July 30th 1998, was the 10th test of the CABRI REPNa programme, devoted to the study of RIA in PWRs. The REPNa10 rod is a stub of an UO2 rod irradiated in the Gravelines 5 power plant up to about 63.5 GWd/tox. The rod stub was manufactured according to the FABRICE process.

The REPNa10 rod (with oxidised and spalled clad) was submitted to an overpower transient with a half-height width (31 ms) intermediate between the REPNa1 (9.5 ms) and REPNa8 (75 ms) ones. The main objective of this test was to study the effect of the pulse width on the behaviour of an oxidised, spalled and highly irradiated clad during a RIA. The REPNa10 transient deposited 107.6 cal/g in the tested fuel at the Peak Power Node.

A rod failure was detected by the microphones 455.9 ms after the TOP onset, which corresponds to a deposited energy of 65.8 cal/g at the Peak Power Node. The failure location deduced from the microphone analysis is 25.9 cm above the Bottom of the Fissile Column. This detection is confirmed by the DND signal close to the REPNa8 one and by the flowmeters.

However, no fuel or gas ejection was detected by the instrumentation (VD, gas passing through the flowmeters,...).

The first visual examinations in a hot cell of the CABRI REPNa10 rod confirm the presence of a crack at the level deduced from the microphone signal analysis.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM: EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS
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6. TYPICAL RUNNING TIME: PHENOMENA TESTED
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7. UNUSUAL FEATURES: SPECIAL FEATURES OF EXPERIMENT
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8. RELATED OR AUXILIARY PROGRAMS: COUNTERPART EXPERIMENTS
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9. STATUS

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10. REFERENCES

A RIA Failure Criterion based on Cladding Strain by C. Vitanza
OECD Halden Reactor Project
Paper presented at the IAEA Technical Committee Meeting on Fuel Behaviour under Transient and LOCA Conditions
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11. TEST DESIGNATION:  REP Na10
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12. PROGRAMMING LANGUAGE(S) USED

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15. ESTABLISHMENT

Institute de Radioprotection et de Surete Nucleaire
CE Cadarache
13108 St PAUL-LEZ-DURANCE Cedex
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16. MATERIAL AVAILABLE
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17. CATEGORIES

Keywords: fuel behaviour, transients.