22
Views
4
CrossRef citations to date
0
Altmetric
Technical Paper

Neutronics of Minor-Actinide Burning Accelerator-Driven Systems with Ceramic Fuel

&
Pages 367-381 | Published online: 10 Apr 2017

References

  • “A Roadmap for Developing Accelerator Transmutation of Waste (ATW) Technology: A Report to Congress,” U.S. Department of Energy (1999).
  • M. DELPECH, “The Am and Cm Transmutation—Physics and Feasibility,” Proc. Int. Conf. Future Nuclear Systems (GLOBAL 99), Jackson Hole, Wyoming, August 29–September 3, 1999, American Nuclear Society (1999) (CD-ROM).
  • J. TOMMASI, M. DELPECH, J-P. GROUILLER, and A. ZAETTA, “Long-Lived Waste Transmutation in Reactors,” Nucl. Technol., 111, 133 (1995).
  • “Review of PNL Study on Transmutation Processing of High Level Waste,” LA-UR-74-74, D. G. FOSTER, Ed., Los Alamos National Laboratory (1974).
  • H. MURATA and T. MUKAIYAMA, “Fission Reactor Studies in View of Reactor Waste Programs,” Atomkenergie-Kerntechnik, 45, 23 (1984).
  • T. TAKIZUKA, I. KANNO, H. TAKADA, T. OGAWA, T. NISHIDA, and Y. KANEKO, “A Study on Incineration Target System,” Proc. 5th Int. Conf. Emerging Nuclear Energy Systems (ICENES 89), p. 70, World Scientific (1989).
  • M. SALVATORES, I. SLESSAREV, G. RITTER, P. FOUGERAS, A. TCHISTIAKOV, G. YOUINOU, and A. ZAETTA, “Long-Lived Radioactive Waste Transmutation and the Role of Accelerator Driven (Hybrid) Systems,” Nucl. Instrum. Methods Phys. Res., Sect. A, 414, 5 (1998).
  • C. RUBBIA, “Fast Neutron Incineration in the Energy Amplifier as Alternative to Geologic Storage,” LHC/97-01 (EET), CERN (1997).
  • K. TSUJIMOTO, T. SASA, K. NISHIHARA, T. TAKIZUKA, and H. TAKANO, “Accelerator-Driven System for Transmutation of High-Level Waste,” Prog. Nucl. Energy, 37, 339 (2000).
  • J. WALLENIUS, K. TUCEK, J. CARLSSON, and W. GUDOWSKI, “Application of Burnable Absorbers in an Accelerator-Driven System,” Nucl. Sci. Eng., 137, 96 (2001).
  • 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).
  • M. ERIKSSON, J. WALLENIUS, M. JOLKKONEN, and J. E. CAHALAN, “Inherent Safety of Fuels for Accelerator-Driven Systems,” Nucl. Technol., 151, 314 (2005).
  • K. TSUJIMOTO, T. SASA, K. NISHIHARA, H. OIGAWA, and H. TAKANO, “Neutronics Design for Lead-Bismuth Cooled Accelerator-Driven System for Transmutation of Minor Actinides,” J. Nucl. Sci. Technol., 41, 21 (2004).
  • D. C. WADE and E. K. FUJITA, “Trends Versus Reactor Size of Passive Reactivity Shutdown and Control Performance,” Nucl. Sci. Eng., 103, 182 (1989).
  • T. H. BAUER, G. R. FENSKE, and J. M. KRAMER, “Cladding Failure Margin for Metallic Fuel in the Integral Fast Reactor,” Proc. 9th Int. Conf. Structural Mechanics in Reactor Technology, Vol. C (1987).
  • R. J. PUIGH and M. L. HAMILTON, Influence of Radiation on Materials Properties: 13th Int. Symp., ASTM STP, Vol. 956, ASTM (1987).
  • Y. S. TANG, R. D. COFFIELD, Jr., and R. A. MARKLEY, Jr., Thermal Analysis of Liquid-Metal Fast Breeder Reactors, American Nuclear Society, La Grange Park, Illinois (1978).
  • M. A. SMITH, E. E. MORRIS, and R. N. HILL, “Physics and Safety Studies of Low Conversion Ratio Sodium-Cooled Fast Reactors,” Proc. Int. Conf. Nuclear Science and Technology (GLOBAL 03), New Orleans, Louisiana, November 16–20, 2003, American Nuclear Society (2003) (CD-ROM).
  • D. C. WADE and R. N. HILL, “The Design Rationale of the IFR,” Prog. Nucl. Energy, 31, 27 (1997).
  • A. WALTAR and A. REYNOLDS, Fast Breeder Reactors, Pergamon Press, Britain (1981).
  • J. WALLENIUS, “Neutronic Aspects of Inert Matrix Fuels for Application in ADS,” J. Nucl. Mater., 320, 142 (2003).
  • M. ERIKSSON, J. WALLENIUS, J. CAHALAN, K. TUCEK, and W. GUDOWSKI, “Safety Analysis of Na and Pb-Bi Coolants in Response to Beam Instabilities,” Proc. 3rd Int. Workshop on Utilization and Reliability of High-Power Proton Accelerators (HPPA02), Santa Fe, New Mexico, May 12–16, 2002.
  • B. CARLUEC and P. ANZIEAU, “Proposal for a Gas-Cooled ADS Demonstrator,” Proc. Int. Conf. Accelerator-Driven Transmutation Technologies and Application (ADTTA 99) (1999).
  • B. F. GROMOV, Y. S. BELOMITCEV, E. I. YEFIMOV, M. P. LEONCHUK, P. N. MARTINOV, Y. I. ORLOV, D. V. PANKRATOV, Y. G. PASHKIN, G. I. TOSHINSKY, and V. V. CHEKUNOV, “Use of Lead-Bismuth Coolant in Nuclear Reactors and Accelerator-Driven Systems,” Nucl. Eng. Des., 173, 207 (1997).
  • M. K. MEYER, “Development and Testing of Metallic Fuels with High Minor Actinide Content,” Proc. 11th Int. Conf. Nuclear Engineering (ICONE-11), Tokyo, Japan, April 20–23, 2003.
  • G. L. HOFMAN, L. C. WALTERS, and T. H. BAUER, “Metallic Fast Reactor Fuels,” Prog. Nucl. Energy, 31, 83 (1997).
  • R. J. M. KONINGS, H. ZHANG, M. E. HUNTELAAR, and E. H. P. CORDFUNKE, “Melting Behaviour of Oxide Systems for Heterogeneous Transmutation of Actinides, III— The System Am-Mg-O,” J. Nucl. Mater., 250, 88 (1997).
  • R. J. M. KONINGS, “Thermochemical and Thermophysical Properties of Curium and Its Oxides,” J. Nucl. Mater., 298, 255 (2001).
  • F. KLAASSEN, K. BAKKER, R. P. C. SCHRAM, R. KLEINMEULEKAMP, R. CONRAD, J. SOMERS, and R. J. M. KONINGS, “Post Irradiation Examination of Irradiated Americium Oxide and Uranium Dioxide in Magnesium Aluminate Spinel,” J. Nucl. Mater., 319, 108 (2003).
  • T. WISS, R. J. M. KONINGS, C. T. WALKER, and H. THIELE, “Microstructure Characterisation of Irradiated Am-Containing MgAl2O4 (EFTTRA-T4),” J. Nucl. Mater., 320, 85 (2003).
  • M. D. FRESHLEY and D. F. CARROLL, “The Irradiation Performance of PuO2/MgO Fuel Material,” Trans. Am. Nucl. Soc., 6, 396 (1963).
  • Y. CROIXMARIE, E. ABONNEAU, A. FERNANDEZ, R. J. M. KONINGS, F. DESMOULIERE, and L. DONNET, “Fabrication of Transmutation Fuels and Targets: The ECRIX and CAMIX-COCHIX Experience,” J. Nucl. Mater., 320, 11 (2003).
  • P. SMITH, “Detailed Core Design of a Reference ADT for Safety Analyses,” “2nd Annual Report of the FUTURE Project,” S. PILlON, Ed., Commissariat à l’Energie Atomique (2004).
  • A. FERNANDEZ, Institute of Transuranium Elements, Personal Communication (2003).
  • P. DEHAUDT, “Composite Fuel Behaviour Under and After Irradiations,” Studies on Fuels with Low Fission Gas Release, IAEA-TECDOC-970, International Atomic Energy Agency (1996).
  • J. WALLENIUS and S. PILLON, “N-15 Requirement for 2nd Stratum ADS Nitride Fuels,” Proc. ANS Meeting on AcceleratorApplications/Accelerator Driven Transmutation Technology Applications (AccApp/ADTTA01), Reno, Nevada, November 11–15, 2001, American Nuclear Society (2001) (CD-ROM).
  • K. RICHTER and C. SARI, “Investigation of the Operational Limits of Uranium-Plutonium Nitride Fuels,” J. Nucl. Mater., 184, 167 (1991).
  • R. THETFORD and M. MIGNANELLI, “The Chemistry and Physics of Modelling Nitride Fuels for Transmutation,” J. Nucl. Mater., 320, 44 (2003).
  • T. OGAWA, T. OHMICHI, A. MAEDA, Y. ARAI, and Y. SUZUKI, “Vaporization Behaviour of (Pu,Am) N,” J. Alloys Compounds, 224, 55 (1995).
  • R. MARGEVICIUS, “AFC Fuels Development Update,” LA-UR-03-0415, Los Alamos National Laboratory (2003).
  • M. TAKANO, A. ITOH, M. AKABORI, K. MINATO, and M. NUMATA, “Study on the Stability of AmN and (Am,Zr)N,” Proc. Int. Conf. Nuclear Science and Technology (GLOBAL 03), New Orleans, Louisiana, November 16–20, 2003, American Nuclear Society (2003) (CD-ROM).
  • M. JOLKKONEN, M. STREIT, and J. WALLENIUS, “Thermo-Chemical Modelling of Uranium-Free Nitride Fuels,” J. Nucl. Sci. Technol., 41, 457 (2004).
  • K. MINATO, M. AKABORI, M. TAKANO, Y. ARAI, K. NAKAJIMA, A. ITOH, and T. OGAWA, “Fabrication of Nitride Fuels for Transmutation of Minor Actinides,” J. Nucl. Mater., 320, 18 (2003).
  • J. WALLENIUS, “CONFIRM: Status and Perspectives,” Proc. Int. Conf. Nuclear Science and Technology (GLOBAL 03), New Orleans, Louisiana, November 16–20, 2003, American Nuclear Society (2003) (CD-ROM).
  • A. MAYORSHIN, V. A. KISLEY, O. V. SHISHALOV, Y. N. EFIMOV, I. Y. ZHEMKOV, A. A. TEYKOVTSEV, V. G. DVORETSKY, G. D. LYADOV, L. M. ZABUDKO, B. D. ROGOZKIN, S. PILLON, and J. NOIROT, “Irradiation of Oxide and Nitride Fuels and also Fuel in the Inert Matrix wiht High Plutonium Content in the BOR-60 Reactor—Status of Russian-French Experiment ‘Bora-Bora,’” Proc. Int. Conf. Nuclear Science and Technology (GLOBAL 03), New Orleans, Louisiana, November 16–20, 2003, American Nuclear Society (2003) (CD-ROM).
  • B. A. HILTON, S. L. HAYES, M. K. MEYER, D. C. CRAWFORD, G. S. CHANG, and R. G. AMBROSEK, “The AFC-Æ and AFC-1F Irradiation Tests of Metallic and Nitride Fuels for Actinide Transmutation,” Proc. Int. Conf. Nuclear Science and Technology (GLOBAL 03), New Orleans, Louisiana, November 16–20, 2003, American Nuclear Society (2003) (CD-ROM).
  • Y. DAI, X. J. DIA, and K. FARRELL, “Mechanical Properties of Modified 9Cr1Mo (T91) Irradiated at 300°C in SINQ Target-3,” J. Nucl. Mater., 318, 192 (2003).
  • C. FAZIO, R. STIEGLITZ, J. KNEBEL, F. GROESCHEL, W. WAGNER, A. STRINNING, H. HEYCK, Y. DAI, B. SMITH, W. LEUNG, G. LAFFONT, T. KIRCHNER, A. GUERTIN, P. AGOSTINI, D. GORSE, T. AUGER, J. VOGT, and A. ALMA-ZOUZI, “The MEGA-PIE Test Project,” Proc. Int. Workshop P&T and ADS Development 2003 (InWor03), Mol, Belgium, October 6–8, 2003, SCK-CEN (2003).
  • N. N. NOVIKOVA, Y. PASHKIN, and V. V. CHEKUNOV, “Some Features of Subcritical Blankets Cooled with Lead Bismuth,” Proc. Int. Conf. Accelerator-Driven Transmutation Technologies and Applications ( ADTTA99) (1999).
  • P. SELTBORG, J. WALLENIUS, K. TUCEK, and W. GUDOWSKI, “Definition and Application of Proton Source Efficiency in Accelerator-Driven Systems,” Nucl. Sci. Eng., 145, 390 (2003).
  • M. ERIKSSON and J. E. CAHALAN, “Inherent Shutdown Capabilities in Accelerator Driven Systems,” Ann. Nucl. Energy, 29, 1689 (2002).
  • A. HOUGH and J. A. C. MARPLES, “The Pseudo Binary Phase Diagrams of PuO2 with Alumina, Beryllia and Magnesia and the Pseudo Ternary PuO2-ThO2-BeO,” J. Nucl. Mater., 15, 298 (1965).
  • R. J. M. KONINGS, H. ZHANG, M. E. HUNTELAAR, and E. H. P. CORDFUNKE, “Melting Behaviour of Oxide Systems for Heterogeneous Transmutation of Actinides, I—The Systems Pu-Al-O and Pu-Mg-O,” J. Nucl. Mater., 249, 223 (1997).
  • D. F. CAROLL, J. Am. Ceram. Soc., 47, 650 (1964).
  • R. KONINGS, Institute of Transuranium Elements, Personal Communication (2003).
  • F. BARBIER, G. BENAMATI, C. FAZIO, and A. RUSANOV, “Compatibility Tests of Steels in Flowing Liquid Lead-Bismuth,” J. Nucl. Mater., 295, 149 (2001).
  • N. LI, X. HE, A. RUSANOV, and A. P. DEMISHONKOV, “Corrosion Tests of US Steels in Lead-Bismuth Eutectic (LBE) and Kinetic Modeling of Corrosion in LBE Systems,” Proc. ANS Topl. Mtg. Accelerator Applications/Accelerator-Driven Transmutation Technology Applications (AccApp/ADTTA01), Reno, Nevada, November 11–15, 2001, American Nuclear Society (2001) (CD-ROM).
  • A. RUSANOV, “Developing and Studying the Cladding Steels for the Fuel Elements of NPIs with Heavy Coolant,” Proc. Heavy Liquid Metal Coolants in Nuclear Technology (HLMC ‘98), Obninsk, Russia, October 5–9, 1998, Institute of Physics and Power Engineering (1998).
  • N. S. CANNON, F. H. HUANG, and M. L. HAMILTON, “Simulated Transient Behaviour of HT-9 Cladding,” Proc. Effects of Radiation on Materials: 14th Int. Symp., Vol. 2, ASTM STP 1046 (1990).
  • N. S. 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. Effects of Radiation on Materials: 15th Int. Symp., ASTM STP 1125 (1992).
  • M. EMBID, R. FERNANDEZ, and E. GONZALES, Proc. 5th Int. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Organization for Economic Cooperation and Development/Nuclear Energy Agency (1998).
  • J. CAHALAN, Argonne National Laboratory, Personal Communication (2005).
  • U.S. Nuclear Regulatory Commission General Design Criterion 11—Reactor Inherent Protection, Appendix A to Part 50: General Design Criteria for Nuclear Power Plants (1999).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.