Toward very high burnups, a strategy for plutonium utilization in pressurized water reactors
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Research context
OpenAlex topics: Nuclear reactor physics and engineering · Nuclear and radioactivity studies · Radioactive contamination and transfer
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References (15)
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2. P. Dehaudt, Proc. Séminaire DRN – Combustibles – Innovation – Absorbants, Lyon (France) 12–13 December, 1996
3. I. Viallard, Modélisation, fabrication et comportement mécanique de combustibles composites a matrice spinelle, in: Proc. Séminaire DRN – Combustibles – Innovation – Absorbants, Lyon (France) 12–13 December, 1996
4. I. Viallard, thesis, INSA, Lyon (France), October, 1996
5. I. Viallard, J.M. Bonnerot, J.P. Fleury, Matériau combustible nucléaire composite et procédé de fabrication du matériau. Brevet CEA N° 96 01500
6. I. Viallard-Munoz, M. Bauer, J.-M. Bonnerot, these Proceedings, p. 34
7. J. Porta, J.Y. Doriath, B. Guigon, S. Baldi, Ph. Dehaudt, A. Mocellin, C. Aillaud, Inert matrix fuels: CERMET, toward an optimized utilization of Pu in PWRs, Neutronic studies and TANOX experiment, in: Proc. IAEA, TCM Fuel Cycle Options for LWR and HWR, Victoria, Canada, 28 April–1 May 1998
8. F. Huet, Fabrication du cermet T2-2 et des CCE. Proc. Séminaire DRN – Combustibles – Innovation – Absorbants, Lyon, France, 12–13 December, 1996
9. J. Porta, C. Aillaud, S. Baldi, these Proceedings, p. 174
10. T. Ogawa, J.S. Tulenko, J. Porta, Innovative fuel forms for better management of nuclear waste, in: Proc. OECD – NEA Workshop on the Back End of Fuel Cycle. Avignon, France, 6–7 October, 1998
11. B. Guigon, R. Girieud, J. Porta, Towards 100% MOX core PWR concept, in: Proceedings of the Internatinal Symposium on Nuclear Fuel Cycle and Reactor Strategy Adjusting to New Realities, IAEA, Vienna, Austria, 3–6 June, 1997
12. J. Porta, S. Baldi, B. Guigon, Some neutronic properties of inert matrix in order to define a 100% IMF core, in: Proceedings of ARWIF'98, OECD/PSI, Villigen, Switzerland, 21–23 October, 1998
13. A. Puill, J. Bergeron, Improved plutonium consumption in a pressurized water reactor, in: Proceedings of the International Conference Global'95 Versailles, France, 11–14 September, 1995, pp. 897–904
14. Puill · Nucl. Technol. · 1997 · 119 · 12310.13182/NT97-A35381 ↗
15. A. Puill, J. Porta, M. Bauer, APA: U free Pu pins in a heterogeneous assembly to improve Pu loading in a PWR. Neutronic, thermohydraulic and manufacturing studies, in: Proc. IAEA – TCM Fuel Cycle Options for LWR and HWR, Victoria, Canada, 28 April–1 May 1998