In a fast breeder reactor, a slow power ramp accident could lead to a local melting of the fuel depending on design and assumptions. If we assume cladding failure in addition to the fuel melting, possibility of fuel ejection from the pin and subsequent consequences of such fuel ejection become important for safety consideration. In order to answer this question, the RB1 and RB2 tests in the CABRI-RAFT program (from 1996 to 2002) were performed under the collaboration between the French ‘Institut de Radioprotection et de Suˆrete´ Nucle´aire’ (IRSN) and JNC. These tests were aiming at a study on impact of fuel pin failure under an overpower condition corresponding to a control-rod withdrawal-type incident leading to fuel melting. Using a special technique, combination of through-cladding failure and fuel melting was realized. In the RB1 test, fuel ejection was prevented under a limited fuel melting condition. On the other hand, significant fuel melting was applied in the RB2 test so as to get the fuel ejection, thereby obtaining information on the fuel ejection behavior. Interpretation for these tests through the detailed experimental data evaluation and the analysis with PAPAS-2S and PHYSURAC codes are performed in this study. Through this study, it is indicated that molten fuel ejection can be prevented with the low smear density fuel as far as the fuel melting is not large for a slit-type cladding defect. Fuel ejection becomes possible in the case of significant fuel melting with a very thin solid fuel shell surrounding the molten fuel cavity. However, the rapidness of the fuel ejection with the low smear density fuel is less pronounced when compared with that of the high smear density fuel. It should be noted that the coolant channel basically kept its wetness by liquid sodium in the RB2 test in the early part of post fuel ejection phase. This fact is encouraging us concerning coolability of the ejected fuel. It is also confirmed that there is considerable DN (Delayed Neutron) -precursor release into the coolant flow already before fuel ejection. This result is useful for evaluation of anomaly detection with DN signal observation.
- Nuclear Engineering Division
The Adventitious-Pin-Failure Study Under a Slow Power Ramp
Fukano, Y, & Charpenel, J. "The Adventitious-Pin-Failure Study Under a Slow Power Ramp." Proceedings of the 12th International Conference on Nuclear Engineering. 12th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 25–29, 2004. pp. 25-32. ASME. https://doi.org/10.1115/ICONE12-49048
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