Nuclear fuel in generation II and III reactors: Research issues related to high burn-up

Energy and Environmental Science

Volumn 4, Issue 5, 2011, Pages 1651-1661

  Degueldre, C ^a   Bertsch, J ^a   Kuri, G ^a   Martin, M ^a  

^a PAUL SCHERRER INSTITUTE   (Switzerland)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 79955684320     PISSN: 17545692     EISSN: 17545706     Source Type: Journal    
DOI: 10.1039/c0ee00476f     Document Type: Article

References (73)

1. C. W. Forsberg, Sustainability by combining nuclear, fossil, and renewable energy sources, Prog. Nucl. Energy, 2009, 51, 192-200.
2. D. Weisser, A guide to life-cycle greenhouse gas (GHG) emissions from electric supply technologies, Energy, 2007, 32, 1543-1559.
3. R. Ekholm, Assessments of nuclear systems, Ann. Nucl. Energy, 1978, 5, 507-526.
4. D. Guentcheva and J. Vira, Economics of nuclear versus coal big is beautiful?, Energy Policy, 1984, 12, 439-451.
5. A. A. Strasser, Quality control of nuclear fuels-technical and economic aspects, J. Nucl. Mater., 1982, 106, 3-12.
6. L. G. Kemeny, A review of the global environmental impact of fossil and nuclear fuels, Math. Comput. Simul., 1982, 24, 194-203.
7. A. Verbruggen, Renewable and nuclear power: a common future?, Energy Policy, 2008, 36, 4036-4047.
8. T. J. Lee, K. Hee Lee and K.-B. Oh, Strategic environments for nuclear energy innovation in the next half century, Prog. Nucl. Energy, 2007, 49, 397-408.
9. D.Warner North, Nuclear waste management: shifting the paradigm, Reliab. Eng. Syst. Saf., 1998, 59, 123-128.
10. G. Kessler, Requirements for nuclear energy in the 21st century nuclear energy as a sustainable energy source, Prog. Nucl. Energy, 2002, 40, 309-325.
11. Y. I. Koryakin, V. V. Batov and V. G. Smirnov, Determination of the optimum burn-up depth and energy content of nuclear fuel by the calculated expenditure method, J. Nucl. Energy, Parts A/B, 1965, 19, 707-711.
12. P. Blair, G. Khvostov, A. Romano, C. Hellwig and R. Chawla, Interpretation of high-burnup fuel annealing tests, J. Nucl. Sci. Technol., 2008, 45, 639-646.
13. J. Noirot, L. Desgranges and J. Lamontagne, Detailed characterisations of high burn-up structures in oxide fuels, J. Nucl. Mater., 2008, 372, 318-339.
14. 2 fuel with a burnup of 7.9% FIMA, J. Nucl. Mater., 1998,
15. 2 fuel pellets with particular reference to results from an XRF investigation, J. Nucl. Mater., 1999, 264, 99-112.
16. 2 structure in LWR fuel, J. Nucl. Mater., 1995, 226, 1-8.
17. 2 fuel, J. Nucl. Mater., 1994, 208, 18-26.
18. Hj. Matzke, Diffusion processes in nuclear fuels, J. Less Common Met., 1986, 121, 537-564.
19. 2 fuel during low-temperature irradiation, J. Nucl. Mater., 1975, 58, 278-284.
20. 2 fuel elements, J. Nucl. Mater., 1962, 7, 225-262.
21. C. Lombardi, L. Luzzi, E. Padovani and F. Vettraino, Thoria and inert matrix fuels for a sustainable nuclear power, Prog. Nucl. Energy, 2008, 50, 944-953.
22. J. S. Herring, P. E. MacDonald, K. D. Weaver and C. Kullberg, Low cost, proliferation resistant, uranium-thorium dioxide fuels for light water reactors, Nucl. Eng. Des., 2001, 203, 65-85.
23. E. I. Vapirev, V. I. Dimitrov, T. J. Jordanov and I. D. Christoskov, Conversion of high enriched uranium in thorium-232-based oxide fuel for light and heavy water reactors: MOX-T fuel, Nucl. Eng. Des., 1996, 167, 105-112.
24. A. Núñez-Carrera, J. L. Lacouture, C. Martin del Campo and G. Espinosa-Paredes, Feasibility study of boiling water reactor core based on thorium-uranium fuel concept, Energy Convers. Manage., 2008, 49, 47-53.
25. C. Degueldre, Zirconia inert matrix for plutonium utilisation and minor actinides disposition in reactors, J. Alloys Compd., 2007, 444-445, 36-41.
26. V. M. Oversby, C. C. McPheeters, C. Degueldre and J. M. Paratte, Control of civilian plutonium inventories using burning in a nonfertile fuel, J. Nucl. Mater., 1997, 245, 17-26.
27. W. J. Carmack, M. Todosow, M. K. Meyer and K. O. Pasamehmetoglu, Inert matrix fuel neutronic, thermalhydraulic, and transient behavior in a light water reactor, J. Nucl. Mater., 2006, 352, 276-284.
28. 2 ceramics for use in LWR inert matrix fuel, J. Nucl. Mater., 2005, 342, 48-62.
29. 2) as fast reactor fuels, Nucl. Eng. Des., 2009, 239, 1916-1924.
30. 3 solid solution formation from wet and dry processes, J. Nucl. Mater., 1991, 178, 204-211.
31. A. Galperin, P. Grimm and V. Raizes, Modelling and verification of the PWR burnable poison designs by ELCOS code system, Ann. Nucl. Energy, 1995, 22, 317-325.
32. F. Franceschini and B. Petrović, Fuel with advanced burnable absorbers design for the IRIS reactor core: combined Erbia and IFBA, Ann. Nucl. Energy, 2009, 36, 1201-1207.
33. A. Talamo, Effects of the burnable poison heterogeneity on the long term control of excess of reactivity, Ann. Nucl. Energy, 2006, 33, 794-803.
34. H. H. Durmazuçar, Ü. Ç olak, B. Sarkaya and G. Gündüz, Burnup characteristics and performance of boron nitride and boron coated urania and urania-gadolinia fuels, Nucl. Eng. Des., 2001, 203, 57-64.
35. 2, J. Nucl. Mater., 2001, 288, 57-65.
36. T. Rogers, J. Ragusa, S. Schultz and R. St Clair, However Optimization of PWR fuel assembly radial enrichment and burnable poison location based on adaptive simulated annealing, Nucl. Eng. Des., 2009, 239, 1019-1029.
37. A. Stanculescu, U. Kasemeyer, J.-M. Paratte and R. Chawla, Conceptual studies for pressurised water reactor cores employing plutonium-erbium-zirconium oxide inert matrix fuel assemblies, J. Nucl. Mater., 1999, 274, 146-152.
38. C. Pistner, W. Liebert and F. Fujara, Neutronics calculations on the impact of burnable poisons to safety and non-proliferation aspects of inert matrix fuel, J. Nucl. Mater., 2006, 352, 268-275.
39. Yu. D. Baranaev, V. V. Popov, V. N. Sharapov and V. M. Troyanov, The feasibility of employing inert matrix ceramic fuels in a Russian light water reactor, J. Nucl. Mater., 2003, 319, 154-158.
40. J. Porta, S. Baldi, J. P. Chauvin and Ph. Fougeras, Qualification of the neutronic efficiency of erbium at zero burnup, Prog. Nucl. Energy, 2001, 38, 355-358.
41. S. Yilmaz, K. Ivanov, S. Levine and M. Mahgerefteh, Development of enriched Gd-155 and Gd-157 burnable poison designs for a PWR core, Ann. Nucl. Energy, 2006, 33, 439-445.
42. J. Porta and M. Asou, Erbium: alternative poison? Stabilisation additive? What future?, Prog. Nucl. Energy, 2001, 38, 347-350.
43. Y. Ronen, L. Golyand and E. Shwageraus, The potential use of 241 Am as proliferation resistant burnable poison in PWRs, Ann. Nucl. Energy, 2010, 37, 201-207.
44. K. Nikitin, M. Saito, V. Artisyuk, A. Chmelev and V. Apse, Advanced U-Np-Pu fuel to achieve long-life core in heavy water reactor, Ann. Nucl. Energy, 1999, 26, 1319-1329.
45. G. S. Chang, Enhancing BWRproliferation resistance fuel with minor actinides, J. Nucl. Mater., 2009, 385, 157-160.
46. 2, J. Nucl. Mater., 1975, 58, 39-46.
47. 2, J. Nucl. Mater., 2004, 325, 141-147.
48. 3, J. Nucl. Mater., 1980, 88, 177-184.
49. C. Rodriguez, A. Baxter, D. McEachern, M. Fikani and F. Venneri, Deep-Burn: making nuclear waste transmutation practical, Nucl. Eng. Des., 2003, 222, 299-317.
50. K. L. Peddicord, R. W. Stratton and J. K. Thomas, Analytical and experimental performance of sphere-pac nuclear fuels, Prog. Nucl. Energy, 1986, 18, 265-299.
51. H. Stehle, Performance of oxide nuclear fuel in water-cooled power reactors, J. Nucl. Mater., 1988, 153, 3-15.
52. 2 fuels at high burn-up, J. Nucl. Mater., 2005, 346, 131-144.
53. 2 nuclear fuel at a burn-up of around 100 MWd/kg HM, J. Nucl. Mater., 2005, 345, 192-205.
54. J. Spino and P. Peerani, Oxygen stoichiometry shift of irradiated LWR-fuels at high burn-ups: review of data and alternative interpretation of recently published results, J. Nucl. Mater., 2008, 375, 8-25.
55. 2 nuclear fuel by EPMA, J. Nucl. Mater., 1999, 275, 56-62.
56. 2 during sintering, J. Nucl. Mater., 2001, 297, 313-326.
57. A. Leenaers, L. de Tollenaere, Ch. Delafoy and S. Van den Berghe, On the solubility of chromium sesquioxide in uranium dioxide fuel, J. Nucl. Mater., 2003, 317, 62-68.
58. P. Blair, A. Romano, C. Hellwig and R. Chawla, Calculations on fission gas behaviour in the high burnup structure, J. Nucl. Mater., 2006, 350, 232-239.
59. C. Degueldre, M. Martin, G. Kuri and D. Grolimund, Plutonium uranium mixed oxide characterisation: a coupled micro-X-ray scattering and absorption investigation, J. Nucl. Mater., 2011, submitted.
60. 2 fuel, J. Alloys Compd., 1998, 271-273, 610-615.
61. 2 solid solutions, J. Alloys Compd., 2007, 444-445, 410-414.
62. C. Degueldre and S. Conradson, Characterization of ternary and quaternary zirconias by XRD and EXAFS: result comparison and data modeling, Appl. Phys. A: Mater. Sci. Process., 2001, 73, 489-494.
63. 2+x binary oxides for x ≤ 0.25, J. Solid State Chem., 2005, 178, 521-535.
64. Y.-W. Lee, H. S. Kim, S. H. Kim, C. Y. Joung, S. H. Na, G. Ledergerber, P. Heimgartner, M. Pouchon and M. Burghartz, Preparation of simulated inert matrix fuel with different powders by dry milling method, J. Nucl. Mater., 1999, 274, 7-14.
65. G. Ledergerber, C. Degueldre, P. Heimgartner, M. A. Pouchon and U. Kasemeyer, Inert matrix fuel for the utilisation of plutonium, Prog. Nucl. Energy, 2001, 38, 301-308.
66. C. Degueldre, T. Arima and Y. W. Lee, Thermal conductivity of zirconia based inert matrix fuel: use and abuse of the formal models for testing new experimental data, J. Nucl. Mater., 2003, 319, 6-14.
67. C. Degueldre and C. Hellwig, Study of a zirconia based inert matrix fuel under irradiation, J. Nucl. Mater., 2003, 320, 96-105.
68. G. R. Lumkin, Physical and chemical characteristics of baddeleyite (monoclinic zirconia) in natural environment: a case study, J. Nucl. Mater., 1999, 274, 206-217.
69. M. Pouchon, E. Curti, C. Degueldre and L. Tobler, The influence of carbonate complexes on the solubility of zirconia: new experimental data, Prog. Nucl. Energy, 2001, 38, 443-446.
70. E. Curti and C. Degueldre, Solubility and hydrolysis of Zr oxides: a review and supplemental data, Radiochim. Acta, 2002, 90, 801-804.
71. C. Ekberg, G. Källvenius, Y. Albinsson and P. L. Brown, Studies on the hydrolytic behavior of zirconium(IV), J. Solution Chem., 2004, 33, 47-79.
72. P. N. Kovalenko and K. N. Bagdasarov, The solubility of Zr hydroxide, Russ. J. Inorg. Chem., 1961, 6, 272-275.
73. J. H. Adair, R. P. Denkewicz and F. J. Arriagada, Precipitation and in-situ transformation in the hydrothermal synthesis of crystalline zirconium dioxide, Ceram. Trans., 1987, 1, 135-145.