Heterogeneous fuels for minor actinides transmutation: Fuel performance codes predictions in the EFIT case study

Annals of Nuclear Energy

Volumn 37, Issue 6, 2010, Pages 867-874

  Calabrese, R ^a   Vettraino, F ^a   Artioli, C ^a   Sobolev, V ^b   Thetford, R ^c  

^a ENEA   (Italy)

^b BELGIAN NUCLEAR RESEARCH CENTRE   (Belgium)

^c SERCO ASSURANCE   (United Kingdom)

Author keywords

Accelerator driven system; Fuel performance code; Heterogeneous fuel; Minor actinides transmutation

Indexed keywords

ACTINIDES; CERAMIC MATERIALS; CERMETS; CODES (SYMBOLS); CONCEPTUAL DESIGN; FAST REACTORS; FUEL STORAGE; FUEL SYSTEMS; FUELS; METALLIC MATRIX COMPOSITES; PLUTONIUM; RADIOACTIVE WASTES; STEEL TESTING;

ACCELERATOR DRIVEN SYSTEM; CLADDING TEMPERATURES; FUEL PERFORMANCE; HETEROGENEOUS FUELS; HIGH LEVEL NUCLEAR WASTES; MINOR ACTINIDES TRANSMUTATION; TECHNICAL PERFORMANCE; THERMOMECHANICAL STATE;

NUCLEAR FUEL REPROCESSING;

EID: 79953162473     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2010.02.009     Document Type: Article

References (39)

1. Bakker, K., Konings, R.J.M., 1998. On the thermal conductivity of inert-matrix fuels containing americium oxide. J. Nucl. Mater. 254, 129-134. (Pubitemid 128414010)
2. 2-x mixed oxide. J. Nucl. Mater. 277, 143-158. (Pubitemid 32211863)
3. EUROTRANS, 2005. Integrated project EUROTRANS: EUROpean research programme for the TRANSmutation of high level nuclear waste in an accelerator driven system. Contract FI6W-CT-2004-516520, EURATOM FP6.
4. Fernandez, A., McGinley, J., Somers, J., Walter, M., 2009. Overview of past and current activities on fuels for fast reactors at the institute for transuranium elements. J. Nucl. Mater. 392, 133-138.
5. Haas, D., Fernandez, A., Staicu, D., Somers, J., Maschek, W., Liu, P., Chen, X., 2008. CERMET fuel behavior and properties in ADS reactors. Energy Convers. Manage. 49, 1928-1933.
6. Hagrman, D.L., Reymann, G.A., Mason, R.E., 1980. MATPRO version 11 (Rev. 1) a Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod Behaviour. EG&G Idaho Inc., Idaho Falls.
7. Jaecki, P., Pillon, S., Warin, D., Hayes, S.L., Kennedy, J.R., Pasamehmetouglu, K., Voit, S.L., Haas, D., Fernandez, A., Arai, Y., 2005. Update on the FUTURIX-FTA experiment in Phénix, Proc. GLOBAL 2005, paper 448, Tsukuba, Japan.
8. Konings, R.J.M., 2001. Thermochemical and thermophysical properties of curium and its oxides. J. Nucl. Mater. 298, 255-268. (Pubitemid 32903665)
9. Lassmann, K., 1978. URANUS-A computer programme for the thermal and mechanical analysis of the fuel rods in a nuclear reactor. Nucl. Eng. Des. 45, 325-342. (Pubitemid 8596792)
10. Lassmann, K., 1992. TRANSURANUS: a fuel rod analysis code ready for use. J. Nucl. Mater. 188, 295-302.
11. Lassmann, K., 2001. The TRANSURANUS code - past, present and future, review article. ITU Annual Report 2001, ITU Joint research Centre, Karlsruhe.
12. Lassmann, K., Moreno, A., 1977. The light-water-version of the URANUS integral fuel-rod code. Atomkernenergie 30 (3), 207-215.
13. Maschek, W., Rineiski, A., Suzuki, T., Mori, M.G., Chen, X., Flad, M., 2003. Safety aspects of oxide fuels for transmutation and utilization in accelerator driven systems. J. Nucl. Mater. 320, 147-155.
14. Maschek, W., Chen, X., Liu, P., Gabrielli, F., Boccaccini, C.M., Rineiski, A., Ottaviani, J.-P., Richaud, J.-C., Donnet, L., Jorion, F., Hiernaut, J.P., Staicu, D., Fernandez, A., Haas, D., Smith, P., Sobolev, V., 2007. A comparative assessment of safety parameters and core behaviour for the CERCER and CERMET oxide fuels proposed for the EFIT (intermediate technical report). Contract FI6W-CT-2004-516520, EURATOM FP6, D 3.10.
15. Maschek, W., Chen, X., Delage, F., Fernandez-Carretero, A., Haas, D., Boccaccini, C.M., Rineiski, A., Smith, P., Sobolev, V., Thetford, R., Wallenius, J., 2008. Accelerator driven systems for transmutation: fuel development, design and safety. Prog. Nucl. Energy 50, 333-340.
16. Matthews, J.R., 1985. The incorporation of detailed physical models in fuel behaviour codes. Nucl. Eng. Des. 88, 111-115. (Pubitemid 15587489)
17. Mignanelli, M.A., Thetford, R., 1993. Chemical modelling in the TRAFIC code. J. Nucl. Mater. 204, 173-179.
18. Mikityuk, K., 2009. Heat transfer to liquid metal: review of data and correlations for tube bundles. Nucl. Eng. Des. 239, 680-687.
19. Miller, J.V., 1967. Estimating Thermal Conductivity of Cermet Fuel Materials for Nuclear Reactor Application. NASA TN D-3898, NASA, Washington, DC.
20. Neeft, E.A.C., Bakker, K., Belvroy, R.L., Tams, W.J., Schram, R.P.C., Conrad, R., van Veen, A., 2003. Mechanical behaviour of macro-dispersed inert matrix fuels. J. Nucl. Mater. 317, 217-225.
21. Ottaviani, J.P., Richaud, J.C., Belin, R., Valenza, Ph., Donnet, L., Jorion, F., Maillard, C., Desmouliere, F., Ronchi, C., Hiernaut, J.P., Thiriet, C., Colle, J.Y., Staicu, D., 2007. Thermal characterization of MgO+(Pu,Am)O2 fuels pellets. Contract FI6W-CT-2004-516520, EURATOM FP6, D 3.40a.
22. RCC-MR, 2002. Design and Construction Rules for Mechanical Components of Nuclear Installations.http://www.afcen.fr/.
23. Rimpault, G., Mansani, L., Cinotti, L., Giraud, B., Ehster-Vignoud, S., Carluec, B., Mueller, A., Artioli, C., Struwe, D., Schikorr, M., Maschek, W., Ait Abderrahim, H., Van den Eynde, G., Sobolev, V., 2006. Definition of the detailed missions of both the Pb-Bi cooled XT-ADS and Pb cooled EFIT and its gas back-up option. Contract FI6W-CT-2004-516520 EURATOM FP6, D 1.1.
24. Rubbia, C., Rubio, J.A., Buono, S., Carminati, F., Fiétier, N., Galvez, J., Gelès, C., Kadi, Y., Klapisch, R., Mandrillon, P., Revol, J.P., Roche, C., 1995. Conceptual Design of a Fast Neutron Operated High Power Energy Amplifier. CERN, CERN/AT/95-44 (ET), Geneva.
25. Sarotto, M., Artioli, C., Peluso, V., 2007. Preliminary neutronic analysis of the three zones EFIT-MgO/Pb core. Technical report, FPN-P9EH-002, ENEA, Bologna.
26. Shinno, H., Kitajima, M., Okada, M., 1988. Thermal stress analysis of high heat flux materials. J. Nucl. Mater. 155-157, 290-294.
27. Sobolev, V., 2005. Thermal and mechanical properties of unirradiated steel T 91. SCK-CEN I-67, Mol.
28. Sobolev, V., 2007. Thermophysical properties of lead and lead-bismuth eutectic. J. Nucl. Mater. 362, 235-247. (Pubitemid 46660039)
29. Sobolev, V., Aoust, Th., Wallenius, J., Fokau, A., Chen, X.-N., Rineiski, A., Boccaccini, C.M., Maschek, W., Delage, F., 2007. Neutronic performances of EFIT-400 (AFTRA) reference cores at the beginning of operation (Intermediate Techinical Report). Contract FI6W-CT-2004-516520, EURATOM FP6, D 3.2.
30. Sobolev, V., Thetford, R., Maschek, W., Chen, X., Delage, F., 2008. Estimation of the thermomechanical performances of the fuel rods of EFIT-400(AFTRA), loaded with the selected TRU-fuels, at the beginning of operation (Intermediate Technical Report). Contract FI6W-CT-2004-516520, EURATOM FP6, D 3.5.
31. Staicu, D., Jeulin, D., Beauvy, M., Laurent, M., Berlanga, C., Negrello, N., Gosset, D., 2001. Effective thermal conductivity of heterogeneous materials: calculation methods and application to different microstructures. High Temp. - High Press. 33, 293-301.
32. Suzuki, M., 2000. Light water reactor fuel analysis code FEMAXI-V (ver.1). JAERIData/Code 2000-030, Tokyo.
33. Thetford, R., Sobolev, V., 2006. Recommended properties of fuel, cladding and coolant for EFIT pre-design. Contract FI6W-CT-2004-516520, EURATOM FP6, D 3.4.
34. 2-x. J. Nucl. Mater. 320, 292-298.
35. Touloukian, Y.S., Buyco, E.H., 1970b. Specific Heat - Nonmetallic Solids. Thermophysical Properties of Matter: TPRC Data Series, vol. 5. Ifi/Plenum Press, New York.
36. Touloukian, Y.S., Powell, R.W., Ho, C.Y., Klemens, P.G., 1970a. Thermal Conductivity - Nonmetallic Solids. Thermophysical Properties of Matter: TPRC Data Series, vol. 2. Ifi/Plenum Press, New York.
37. Touloukian, Y.S., Kirby, R.K., Taylor, R.E., Lee, T.Y.R., 1970c. Thermal Expansion - Nonmetallic Solids. Thermophysical Properties of Matter: TPRC Data Series, vol. 13. Ifi/Plenum Press, New York.
38. Wallenius, J., Pillon, S., Zaboudko, L., 2006. Fuels for accelerator-driven systems. Nucl. Instrum. Methods Phys. Res. Sect. A 562, 625-629. (Pubitemid 43831298)
39. Weisenburger, A., Heinzel, A., Müller, G., Muscher, H., Rousanov, A., 2008. T 91 cladding tubes with and without modified FeCrAlY coatings exposed in LBE at different flow, stress and temperature conditions. J. Nucl. Mater. 376, 274-281.