Skip to main content Accessibility help

Assessment of the Insertion of Reprocessed Fuels and Combined Thorium Fuel Cycles in a PWR System

  • Fabiana. B. A. Monteiro (a1) (a2), Rochkhudson. B. de Faria (a1), Ângela Fortini (a1), Clarysson A. M. Da Silva (a1) and Cláubia Pereira (a1) (a2)...


The insertion of reprocessed fuel spiked with thorium in a typical PWR fuel element considering (TRU-Th) cycle was simulated using different fissile materials that varied from 5.5% to 7.0%. The reprocessed fuels were obtained using the ORIGEN 2.1 code from a burned PWR standard fuel (33,000 MWd/tHM burned), with 3.1% of initial enrichment, which was remained in the cooling pool for five years and then reprocessed using UREX+ technique. The kinf, hardening spectrum and the fuel evolution during the burnup were evaluated. This study was performed using the SCALE 6.0


Corresponding author


Hide All



Hide All
1. Maiorino, J. R. and Carluccio, T., “A Review of Thorium Utilization as an option for Advanced Fuel Cycle- Potential Option for Brazil in the Future”, ANES 2004: Americas Nuclear Energy Symposium, Miami Beach, Florida, 36 October (2004).
2. Pinheiro, R.B., Carneiro, F.A.N., Lameiras, F.S., Ferreira, R.A.N., Ferraz, W.B., Dias, M.S., Soares, M.L.L., de Andrade, E.P., Mascarenhas, H.A., dos Santos, A.M.M, Pinto, L.C.M., Santos, A., Filgueiras, S.A.C., de O. Lopes, M.J., Peehs, M., Scholosser, G., Wunderlich, F., Gross, H., Doer, W., Gartner, M., Kaspar, G., Finnemann, H., Porsch, D., Hrovat, M., Kadner, M., Marly, V., Reichardt, K., Brodda, B.G., Zimmer, E., “Final Report (1979-1988)”, German-Brazilian Cooperation in Scientific Research and Technological Development, Program of Research and Development on the Thorium Utilization in PWRs, Herausgegeben Von Der Kernforschungsanlage Julich GmbH, ZENTRALBIBLIOTHEK Titelsatz: Graphische Betriebe Der KFA, page 31, 1988.
3. IAEA, “Spent Fuel Reprocessing Options”, Nuclear Fuel Cycle and Materials Section International Atomic Energy Agency (2008).
4. Weaver, K. D. and Herring, J. S., “Performance of Thorium-Based Mixed Oxide Fuels for the Consumption of Plutonium in Current and Advanced ReactorsInternational Congress On Advanced Nuclear Power Plants (ICAPP) 2002 ANS Annual Meeting June 9, 2002.
5. Pereira, Claubia ; LEITE, EUZIMAR M. ; FARIA, EDUARDO F.. Waste analysis generated by alternative reprocessing fuels from pressurised water reactions. Annals of Nuclear Energy, v. 27, p. 449464, 2000.
6. Pereira, C. ; LEITE, E. M.. Non-Proliferating Reprocessed Nuclear Fuels In Pressurized Water Reactors: Fuel Cycle Options. Annals of Nuclear Energy, Grã-Bretanha, v. 25, n.12, p. 937962, 1998.
7. Pereira, C. ; COTA, S. D. S.. Neutronic Evaluation Of The Nonproliferating Reprocessed Nuclear Fuelsin Pressurized Water Reactors.. Annals of Nuclear Energy, Grã-Bretanha, v. 24, n.10, p. 829834, 1997.
8. Cota, S. and Pereira, C., “Neutronic evaluation of the non-proliferating reprocessed nuclear fuels in pressurized water reactors,” Annals of Nuclear Energy, vol. 24, no. 10, pp. 829834 (1997).
9. , M. F. SIMPSON and , J. D. LAW. “Nuclear Fuel Reprocessing”. INL/EXT-10-17753. Fuel Cycle Science and Technology Division. Idaho National Laboratory. Idaho Falls, Idaho 83415. February (2010).
10. ARGONNE NATIONAL LABORATORY. “Lab-Scale Demonstration of the UREX+ Process”. WM’04 Conference, February 29 – March 4, Tucson, AZ. USA (2004).
11. FEENDER, J. S.. “Safeguards for the Uranium Extraction (UREX) +1A Process”. Thesis Submitted and Approved by the Office of Graduate Studies of Texas A&M University. May (2010).
12. Lung, M., “A Present Review of the Thorium Nuclear Fuel Cycle”, Nuclear science and Technology European Commission (1997).
13. Romanello, V., Savatores, M., Schwenk-Ferrero, A., Gabrielli, F., Maschev, W., Vessonji, B., “Comparative Study of Fast Critical Burner Reactor and Subcritical Accelerator Driven Systems and the Impact on Transuranics Inventory in a Regional Fuel Cycle”, Elsevier, Nuclear Engineering and Design, vol. 241, pp. 433443 (2011).Gfgfhfh
14. Croff, A. G., A User's Manual for the ORIGEN2 Computer Code, Oak Ridge National Laboratory, Report ORNL/TM-7175 (1980).
15. ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT. NUCLEAR ENERGY AGENCY. “Burn-up Credit Criticality Benchmark. Phase IV-A. Reactivity Prediction Calculations for Infinite Arrays of PWR MOX Fuel Pin Cells”. NEA/NSC/DOC(2003)3. ISBN 92-64-02123-X. France (2003).
16. Oak Ridge National Laboratory, SCALE Cross-Section Libraries, ORNL/TM-2005/39, Version 6, Vol. III, Sect. M4, January (2009).
17. Eletrobrás Termonuclear, S.A., “Final safety Analysis Report – FSAR Angra 2”, Eletronuclear, Rio de Janeiro (1999).
18. Bowman, S. M., “KENO-VI Primer: A Primer for Criticality Calculations with SCALE/KENO - VI Using GeeWiz”, ORNL/TM-2008/069.
19. Goluoglu, S., Hollenbach, D. F. and Petrie, L. M., “CSAS6: Control Module For Enhanced Criticality Safety Analysis With KENO-VI”, ORNL/TM-2008/039.
20. DeHart, M. D., “Triton: a two-dimensional transport and depletion module for characterization of spent nuclear fuel”, ORNL/TM-2005/39, Version 6, Vol. I, Sect. T1, Nuclear Science and Technology Division.
21. Petrie, L. M., Fox, P. B., Lucius, K., “Standard Composition Library”, ORNL/TM-2005/39, Version 6,Vol. III, Sect. M8, Nuclear Science and Technology Division.


Assessment of the Insertion of Reprocessed Fuels and Combined Thorium Fuel Cycles in a PWR System

  • Fabiana. B. A. Monteiro (a1) (a2), Rochkhudson. B. de Faria (a1), Ângela Fortini (a1), Clarysson A. M. Da Silva (a1) and Cláubia Pereira (a1) (a2)...


Full text views

Total number of HTML views: 0
Total number of PDF views: 0 *
Loading metrics...

Abstract views

Total abstract views: 0 *
Loading metrics...

* Views captured on Cambridge Core between <date>. This data will be updated every 24 hours.

Usage data cannot currently be displayed