Neutronic and safety aspects of a gas-cooled subcritical core for minor actinide transmutation

Nuclear Technology

Volumn 154, Issue 1, 2006, Pages 41-51

  Westlén, Daniel ^a   Wallenius, Janne ^a  

^a ROYAL INSTITUTE OF TECHNOLOGY   (Sweden)

Author keywords

Accelerator driven systems; Helium cooling; Minor actinide fuel

Indexed keywords

ACTINIDES; COOLING; HEAT EXCHANGERS; MONTE CARLO METHODS; NUCLEAR REACTORS; PLUTONIUM; URANIUM;

ACTINIDE TRANSMUTATION; DOPPLER FEEDBACK; GAS-COOLED ACCELERATOR-DRIVEN SYSTEM;

NUCLEAR FUELS;

EID: 33645918000     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT06-A3716     Document Type: Article

References (37)

1. EUROPEAN TECHNICAL WORKING GROUP ON ADS, "A European Roadmap for Developing Accelerator Driven Systems (ADS) for Nuclear Waste Incineration," ISBN 88-8286-008-6, ENEA (2001).
2. J. P. GROUILLER, S. PILLON, C. DE SAINT JEAN, F. VARAINE, L. LEYVAL, G. VAMBENEPE, and B. CARLIER, "Minor Actinides Transmutation Scenario Studies with PWRs, FRs and Moderated Targets," J. Nucl. Mater., 320, 163 (2003).
3. A. VASILE, P. DUFOUR, H. GOLFIER, J. P. GROUILLER, J. L. GUILLET, C. POINOT, G. YOUINOU, and A. ZAETTA, "Advanced Fuels for Plutonium Management in Pressurized Water Reactors," J. Nucl. Mater., 319, 173 (2003).
4. J. WALLENIUS and M. ERIKSSON, "Neutronics of Minor-Actinide Burning Accelerator-Driven Systems with Ceramic Fuel," Nucl. Technol., 152, 367 (2005).
5. "Review of PNL Study on Transmutation Processing of High Level Waste," D. G. FOSTER, Ed., LA-UR-74-74, Los Alamos National Laboratory (1974).
6. T. TAKIZUKA, H. TAKADA, I. KANNO, T. NISHIDA, M. AKABORI, and Y. KANEKO, "Conceptual Design of Transmutation Plant," Proc. Specialist Mtg. Accelerator-Driven Transmutation Technology for Radwaste and Other Applications, Stockholm, Sweden, June 24-28, 1991.
7. K. TSUJIMOTO, T. SASA, K. NISHIHARA, H. OIGAWA, and H. TAKANO, "Neutronics Design for Lead-Bismuth Cooled Accelerator-Driven System for Transmutation of Minor Actinide," J. Nucl. Sci. Technol., 41, 1, 21 (2004).
8. B. CARLUEC and P. ANZIEU, "Proposal for a Gas Cooled ADS Demonstrator," Proc. 3rd Int. Conf. Accelerator Driven Transmutation Technologies and Applications (ADTTA'99), Praha, Czech Republic, June 7-11, 1999.
9. G. B. MELESE-D'HOSPITAL, "Review of Gas Cooled Reactors Thermal Hydraulics," Proc. ANS/ASME/NRC Int. Topl. Mtg. Nuclear Reactor Thermal-Hydraulics, Saratoga Springs, New York, October 5-8, 1980.
10. J.P. GAILLARD, G. MIGNOT, and A. CONTI, "Thermal-Hydraulic Design of a Gas Cooled Fast Reactor," Proc. 2003 Int. Congress Advances in Nuclear Power Plants (ICAP '03), Córdoba, Spain, May 4-7, 2003, American Nuclear Society (2003) (CD-ROM).
11. E. E. FELDMAN and T. Y. C. WEI, "Cold-Finger Concept for Passive Decay Heat Removal in Gas-Cooled Reactors," Trans. Am. Nucl. Soc., 88, 681 (2003).
12. P. FORTESCUE, G. B. MELESE-D'HOSPITAL, J. PEAK, and L. MEYER, "A Developmental Gas-Cooled Fast Breeder Reactor Plant," Proc. Nuclex 69, Basel, Switzerland, October 6-11, 1969.
13. J. B. DEE and G. B. MELESE-D'HOSPITAL, "Part 1 - The 300 MW(e) GCFR Demonstration Plant," Mech. Eng., 94, 18 (1972).
14. M. ERIKSSON, J. WALLENIUS, M. JOLKKONEN, and J. E. CAHALAN, "Inherent Safety of Fuels for Accelerator-Driven Systems," Nucl. Technol., 151, 314 (2005).
15. N. CHAUVIN, J. C. GARNIER, J. L. SERAN, P. MARTIN, and P. BROSSARD, "Requirements for Fuel and Structural Materials for Gas Cooled Fast Reactor (GFR), Preliminary Design," Proc. Global 2003, New Orleans, Louisiana, November 16-20, 2003, American Nuclear Society (2003) (CD-ROM).
16. J. WALLENIUS, "Neutronic Aspects of Inert Matrix Fuels for Application in ADS," J. Nucl. Mater., 320, 142 (2003).
17. 14C Production in Nitride Fuel Cycle Scenarios," J. Nucl. Mater. (submitted for publication).
18. R. THETFORD and M. MIGANELLI, "The Chemistry and Physics of Modelling Nitride Fuels for Transmutation," J. Nucl. Mater., 320, 44 (2003).
19. L. ZABOUDKO, "Status of CEA-Minatom Collaborative Experiment Bora-Bora: Fuels with High Plutonium Content," Proc. ANL Transmuter Fuel Development Workshop, Idaho Falls, Idaho, November 19-21, 2001.
20. J. CETNAR, J. WALLENIUS, and W. GUDOWSKI, "MCB: A Continuous Energy Monte-Cario Burnup Simulation Code, Actinide and Fission Product Partitioning and Transmutation," Proc. 5th Int. Information Exchange Mtg., Mol, Belgium, November 25-27, 1998, p. 523, Organization for Economic Cooperation and Development/Nuclear Energy Agency (1998).
21. "NEA-1643 MCBIC," available on the Internet at (http://www.nea.fr/abs/html/nea-1643.html) (Feb. 15, 2005).
22. "Actinide and Fission Product Partitioning and Transmutation - Status and Assessment Report," Organization for Economic Cooperation and Development/Nuclear Energy Agency (1999).
23. M. DALLE DONNE and L. MEYER, "Turbulent Convective Heat Transfer from Rough Surfaces with Two-Dimensional Rectangular Ribs," Int. J. Heat Mass Transfer, 20, 583 (1977).
24. M. KAVIANY, Principles of Heat Transfer in Porous Media, Springer-Verlag, New York (1999).
25. CRC Handbook of Chemistry and Physics, 73rd ed., D. R. LIDE, Ed., CRC Press, Boca Raton, Florida (1992).
26. N. SCOTT CANNON, F. H. HUANG, and M. L. HAMILTON, "Transient and Static Mechanical Properties of D9 Fuel Pin Cladding and Duct Material Irradiated to High Fluence," Proc. 15th ASTM Int. Symp. Effects of Radiation on Materials, Nashville, Tennessee, 1992, ASTM STP 1125, American Society for Testing and Materials (1992).
27. R. J. PUIGH and M. L. HAMILTON, "In-Reactor Creep Rupture Behavior of the D 19 and 316 Alloys," Proc. Influence of Radiation on Material Properties: 13th Int. Symp. (Part II), Seattle, Washington, June 23-25, 1986, American Society for Testing and Materials (1987).
28. J. L. SÉRAN et al., "Behaviour Under Neutron Irradiation of the 15-15 Ti and Em 10 Steels Used as Standard Materials of the PHÉNIX Fuel Subassembly," Proc. 15th ASTM Int. Symp. Effects of Radiation on Materials, Nashville, Tennessee, 1992, ASTM STP 1125, American Society for Testing and Materials (1992).
29. GROUPE DE TRAVAIL RAMSES 2, "Règles d'analyse mécaniques des stuctures irradiées," CEA R.5618, Commissariat à l'Energie Atomique.
30. G. B. MELESE-D'HOSPITAL, "Natural Circulation Cooling Potential of CO2 and He for GCFR's," Proc. ANS/ASME/NRC Int. Topl. Mtg. Nuclear Reactor Thermal-Hydraulics, Saratoga Springs, New York, October 5-8, 1980.
31. N. E. TODREAS and M. S. KAZIMI, Nuclear Systems I - Thermal Hydraulic Fundamentals, Hemisphere Publishing Company, New York (1989).
32. A. E. WALTAR and A. B. REYNOLDS, Fast Breeder Reactors, Pergamon Press, New York (1981).
33. M. A. HASSAN and K. REHME, "Heat Transfer near Spacer Grids in Gas-Cooled Rod Bundles," Nucl. Technol., 52, 401 (1981).
34. The Nuclear Fuel of Pressurized Water Reactors and Fast Reactors - Design and Behavior, H. BAILLY, D. MÉNESSIER, and C. PRUNIER, Eds., Commissariat à l'Energie Atomique (1999).
35. H. W. WIESE, "Actinide Transmutation Proper ties of Thermal and Fast Fission Reactors Including Multiple Recycling," J. Alloys Compounds, 271, 522 (1998).
36. W. S. YANG and H. S. KHALIL, "Blanket Design Studies of a Lead-Bismuth Eutectic-Cooled Accelerator Transmutation of Waste System," Nucl. Technol., 135, 162 (2001).
37. C. W. HUNTER, R. L. FISH, and J. J. HOLMES, "Mechanical Properties of Unirradiated Fast Reactor Cladding During Simulated Overpower Transients," Nucl. Technol., 27, 376 (1975).