Thermomechanical loading applied on the cladding tube during the pellet cladding mechanical interaction phase of a rapid reactivity initiated accident
Source abstract
Abstract
Abstract Calculations of the CABRI REP-Na5 pulse were performed with the ALCYONE code in order to determine the evolution of the thermomechanical loading applied on the cladding tube during the Pellet–Cladding Mechanical Interaction (PCMI) phase of a rapid Reactivity Initiated Accident (RIA) initiated at 280 °C that lasted 8.8 ms. The evolution of the following parameters are reported: the cladding temperature, heating rate, strain rate and loading biaxiality. The impact of these parameters on the cladding mechanical behavior and fracture are then briefly reviewed.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · High Temperature Alloys and Creep · Hydrogen embrittlement and corrosion behaviors in metals
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (23)
Show source-provided references
1. NEA · 2010
2. T. Fuketa, T. Sugiyama, Current RIA-related regulatory criteria in Japan and their technical basis, in: Workshop RIA, Paris, France, 2009.
3. T. Sugiyama, Y. Udagawa, M. Suzuki, F. Nagase, Influence of coolant temperature and power pulse width on fuel failure limit under reactivity-initiated accident conditions, in: International Topical Meeting on Light Water Reactor Fuel Performance, Chengdu, China, 2011.
4. Cazalis · Nucl. Technol. · 2007 · 157 · 21510.13182/NT07-A3814 ↗
5. J. Sercombe, E. Federici, M. Le Saux, B. Michel, C. Poussard, 1D and 3D Modeling of PCMI during a RIA with ALCYONE V1.1, in: International Topical Meeting on Light Water Reactor Fuel Performance, Orlando, Florida, 2010.
6. Sercombe · Nucl. Eng. Des. · 2012 · 242 · 16410.1016/j.nucengdes.2011.08.069 ↗
7. Le Saux · J. Nucl. Mater. · 2008 · 378 · 6010.1016/j.jnucmat.2008.04.017 ↗
8. J. Papin, B. Cazalis, J. Frizonnet, E. Federici, F. Lemoine, Synthesis of CABRI-RIA tests interpretation, in: Eurosafe Meeting, Paris, France, 2003.
9. Papin · Nucl. Technol. · 2007 · 157 · 23010.13182/NT07-A3815 ↗
10. Le Saux · Eng. Fail. Anal. · 2010 · 17 · 68310.1016/j.engfailanal.2009.07.001 ↗
11. A. Hellouin de Menibus, FailureFormation de blisters d’hydrures et effet sur la rupture de gaines en Zircaloy-4 en conditions d’accident d’injection de reactivite, Ph.D. thesis, Mines Paristech, Centre des Materiaux, 2012.
12. Hellouin de Menibus · Mater. Sci. Eng.: A · 2014 · 604 · 5710.1016/j.msea.2014.02.075 ↗
13. Kearns · J. Nucl. Mater. · 1968 · 27 · 6410.1016/0022-3115(68)90008-1 ↗
14. Ribis · J. ASTM Int. · 2008 · 5 · 110.1520/JAI101118 ↗
15. K. Yueh, V. Grigoriev, Y. Lin, D. Lutz, D. Schrire, Zircaloy-2 ductility recovery under RIA transient conditions, in: International Topical Meeting on Light Water Reactor Fuel Performance, Chengdu, China, 2011.
16. A. Hellouin de Menibus, Q. Auzoux, J. Besson, J. Crepin, Temperature increase of Zircaloy-4 cladding tubes due to plastic heat dissipation during tensile tests at reactivity initiated accident representative strain rates, in: Light Water Reactor Fuel Performance Meeting, American Nuclear Society, Charlotte, North Carolina, USA, 2013.
17. Rice · J. Mech. Phys. Solids · 1969 · 17 · 20110.1016/0022-5096(69)90033-7 ↗
18. Yunchang · Metall. Trans. A · 1985 · 16 · 67510.1007/BF02814242 ↗
19. Maki · J. Nucl. Sci. Technol. · 1975 · 12 · 42310.1080/18811248.1975.9733131 ↗
20. T. Andersson, A. Wilson, Ductility of Zircaloy canning tubes in relation to stress ratio in biaxial testing, in: J. Schemel, T. Papazoglou (Eds.), 4th International Symposium on Zirconium in the Nuclear Industry, ASTM STP681, 1979, pp. 60–71.10.1520/STP36672S ↗
21. E. Kaplar, L. Yegorova, K. Lioutov, A. Konobeyev, A. Jouravkova, V. Smirnov, A. Goryachev, V. Prokhorov, O. Makarov, S. Yeremin, A. Svyatkin, Mechanical properties of unirradiated and irradiated Zr–1Nb cladding: procedures and results of low temperature biaxial burst tests and axial tensile tests, Tech. Rep. NUREG/IA-0199, U.S. Nuclear regulatory Commission, 2001.
22. A. Hellouin de Menibus, Q. Auzoux, J. Besson, J. Crepin, Hydride blisters formation, characterization and effect on the fracture of Zircaloy-4 cladding tubes under reactivity initiated accident conditions, in: Light Water Reactor Fuel Performance Meeting, American Nuclear Society, Charlotte, North Carolina, USA, 2013.10.1016/j.jnucmat.2014.03.006 ↗
23. The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident (RIA)10.1016/j.jnucmat.2011.03.015 ↗