全部 标题 作者
关键词 摘要

OALib Journal期刊
ISSN: 2333-9721
费用:99美元

查看量下载量

相关文章

更多...

A Compact Gas-Cooled Fast Reactor with an Ultra-Long Fuel Cycle

DOI: 10.1155/2013/618707

Full-Text   Cite this paper   Add to My Lib

Abstract:

In an attempt to allow nuclear power to reach its full economic potential, General Atomics is developing the Energy Multiplier Module (EM2), which is a compact gas-cooled fast reactor (GFR). The EM2 augments its fissile fuel load with fertile materials to enhance an ultra-long fuel cycle based on a “convert-and-burn” core design which converts fertile material to fissile fuel and burns it in situ over a 30-year core life without fuel supplementation or shuffling. A series of reactor physics trade studies were conducted and a baseline core was developed under the specific physics design requirements of the long-life small reactor. The EM2 core performance was assessed for operation time, fuel burnup, excess reactivity, peak power density, uranium utilization, etc., and it was confirmed that an ultra-long fuel cycle core is feasible if the conversion is enough to produce fissile material and maintain criticality, the amount of matrix material is minimized not to soften the neutron spectrum, and the reactor core size is optimized to minimize the neutron loss. This study has shown the feasibility, from the reactor physics standpoint, of a compact GFR that can meet the objectives of ultra-long fuel cycle, factory-fabrication, and excellent fuel utilization. 1. Introduction Nuclear power has much to offer in addressing the nation’s energy security needs in an environmentally acceptable manner. However, today’s nuclear power has its own challenges in the management of nuclear waste from both the front end and back end of the fuel cycle, along with huge upfront financial investment and competing against other energy resources-electricity generation cost. Currently, the most prevailing commercial reactor type is the Light Water Reactor (LWR), and it is expected that the advanced LWR will be introduced in the very near future based on proven technologies [1]. However, the International Atomic Energy Agency (IAEA) predicts that for the longer term the focus will be on innovative designs to provide increased benefits in terms of safety and security, nonproliferation, waste management, resource utilization, and economics, as well as to offer a variety of energy products and flexibility in design, siting, and fuel cycle options [2]. Small reactors are defined as reactors with an equivalent electric output of less than 300?MW. The small modular reactor has been developed since the 1950s when the United States (US) Army and Navy initiated research programs for the design and test of various small nuclear reactors [3]. The Army was interested in producing electricity in

References

[1]  C. K. Paulson, “Westinghouse AP1000 electrical generation costs—meeting marketplace requirements,” in Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP '02), Hollywood, Fla, USA, 2002.
[2]  “Innovative small and medium sized reactors: design features, safety approaches, and R&D trends,” IAEA-TECDOC-1451, International Atomic Energy Agency, 2005.
[3]  Report to Congress on Small Modular Nuclear Reactors, U.S. Department of Energy, 2001.
[4]  Design Features to Achieve Defense in Depth in Small and Medium Sized Reactors, Nuclear Energy Series no. NP-T-2.2, International Atomic Energy Agency, 2009.
[5]  Status of Innovative Small and Medium Sized Reactor Designs 2005: Reactors with Conventional Refuelling Schemes, IAEA-TECDOC Series no. 1485, International Atomic Energy Agency, 2006.
[6]  R. L. Black, “Small modular reactor U.S. market and licensing possibilities,” in Proceedings of the American Nuclear Society Annual Meeting, Atlanta, Ga, USA, June 2009.
[7]  Status of Small Reactor Designs without On-Site Refuelling, IAEA-TECDOC Series no. 1536, International Atomic Energy Agency, 2007.
[8]  D. J. Senor, C. L. Painter, K. J. Geelhood, et al., “A new innovative spherical cermet nuclear fuel element to achieve an ultra-long core life for use in grid-appropriate LWRs,” PNNL-16647, Pacific Northwest National Laboratory, 2007.
[9]  A. A. Belyaev, A. V. Kurachenkov, Y. K. Panov, and O. B. Samoilov, “Nuclear energy sources on the basis of integral reactors,” Nuclear Engineering and Design, vol. 173, no. 1–3, pp. 131–141, 1997.
[10]  K. Hibi, H. Takimoto, M. Chaki, M. Matsuura, and K. Moriya, “Development of the package-reactor (1) -reactor for pioneering new nuclear markets,” Progress in Nuclear Energy, vol. 47, no. 1–4, pp. 115–122, 2005.
[11]  M. Kambe, H. Tsunoda, K. Mishima, and T. Iwamura, “RAPID-L operator-free fast reactor concept without any control rods,” Nuclear Technology, vol. 143, no. 1, pp. 11–21, 2003.
[12]  F. Sefidvash, “Status of the small modular fluidized bed light water nuclear reactor concept,” Nuclear Engineering and Design, vol. 167, no. 2, pp. 203–214, 1996.
[13]  I. V. Dulera, A. Basak, P. P. Kelkar, and R. K. Sinha, “Compact high temperature reactor (CHTR),” in Proceedings of the 16th Annual Conference of Indian Nuclear Society (INSAC '05), Mumbai, India, November 2005.
[14]  Z. Su’ud, “Advanced SPINNORs concept and the prospect of their deployment in remote area,” in Proceedings of the International Conference on Advances in Nuclear Science and Engineering (ICANSE '07), Bandung, Indonesia, November 2007.
[15]  Z. Su’ud and H. Sekimoto, “Preliminary design study of the ultra long life fast reactor,” Nuclear Engineering and Design, vol. 140, no. 2, pp. 251–260, 1993.
[16]  M. Kawashima, K. Aoki, K. Arie, and Y. Tsuboi, “Neutronic feasibility of an LMFBR super long-life core (SLLC),” Nuclear Engineering and Design, vol. 106, no. 3, pp. 357–373, 1988.
[17]  T. K. Kim and T. A. Taiwo, “Feasibility study of ultra-long life fast reactor core concept,” in Proceedings of the Advances in Reactor Physics to Power the Nuclear Renaissance (PHYSOR '10), pp. 1756–1766, Pittsburgh, Pa, USA, May 2010.
[18]  J. Gilleland, C. Ahlfeld, D. Dadiomov et al., “Novel reactor designs to burn non-fissile fuels,” in Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP '08), Anaheim, Calif, USA, June 2008.
[19]  A. E. Waltar and A. B. Reynolds, Fast Breeder Reactors, Pergamon Press, New York, NY, USA, 1981.
[20]  P. Yarsky, Core design and reactor physics of a breed and burn gas-cooled fast reactor [Ph.D. thesis], Massachusetts Institute of Technology, 2005.
[21]  P. W?lti and P. Koch, “MICROX: a two-region flux spectrum code for the efficient calculation of group cross sections,” General Atomic Report GA-A10827, Gulf General Atomic Company, 1972.
[22]  G. D. Joanou and J. S. Dudek, “GAM II, a B3 code for the calculation of fast neutron spectra and associated multigroup constants,” General Atomic Report GA-4265, Gulf General Atomic Company, 1963.
[23]  G. D. Joanou, C. V. Smith, and H. A. Vieweg, “GATHER-II, an IBM-7090 code for the calculation of thermal neutron spectra and associated multigroup constants,” General Atomic Report GA-4132, Gulf General Atomic Company, 1963.
[24]  C. A. Stevens and C. V. Smith, “GAROL: a computer program for evaluating resonance absorption including resonance overlap,” Tech. Rep. GA-6637, Gulf General Atomic Company, 1965.
[25]  K. L. Derstine, “DIF3D: a code to solve one-, two-, and three-dimensional finite difference diffusion theory problems,” Tech. Rep. ANL-82-64, Argonne National Laboratory, 1984.
[26]  R. Sherman, “PCBURP: a macroscopic cross section generation and nuclide depletion program for use with DIF3D,” 21C024, General Atomics, 1996.
[27]  T. Nakagawa, H. D. Lemmel, and P. K. McLaughlin, “The JENDLE-3. 3 fission-product data library,” IAEA-NDS-138, International Atomic Energy Agency, 2003.
[28]  A. G. Croff, “A user’s manual for the ORIGEN2 computer code,” Tech. Rep. ORNL/TM-7175, Oak Ridge National Laboratory, 1980.
[29]  H. Choi, “Physics model of a gas-cooled fast reactor: review and assessment,” in Proceedings of the International Topical Meeting on Advances in Reactor Physics (PHYSOR '12), Knoxville, Tenn, USA, April 2012.
[30]  D. B. Pelowitz, Ed., “MCNPXTM user’s manual,” Tech. Rep. LA-CP-05-0369, Los Alamos National Laboratory, 2005.
[31]  J. Hou, K. Ivanov, and H. Choi, “MICROX-2 cross section library based on ENDF/B-VII,” in Proceedings of the International Topical Meeting on Advances in Reactor Physics (PHYSOR '12), Knoxville, Tenn, USA, April 2012.
[32]  J. Hou, K. Ivanov, and H. Choi, “Self-shielding models of MICROX-2 code,” in Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering (M&C '13), Sun Valley, Idaho, USA, May 2013.
[33]  L. L. Snead, T. Nozawa, Y. Katoh, T. S. Byun, S. Kondo, and D. A. Petti, “Handbook of SiC properties for fuel performance modeling,” Journal of Nuclear Materials, vol. 371, no. 1–3, pp. 329–377, 2007.
[34]  A. Kohyama, Y. Katoh, L. L. Snead, and R. H. Jones, “Development of SiC/SiC composite for fusion application,” in Proceedings of the 18th International Atomic Energy Agency Fusion Energy Conference, Sorrento, Italy, October 2000.
[35]  H. Choi, D. W. McEachern, and R. W. Schleicher, “Energy Multiplier Module (EM2) recycling fuel cycles,” in Proceedings of the 1st Annual ANS SMR Conference, Washington, DC, USA, October-November 2011.
[36]  W. E. Cummins, M. M. Corletti, and T. L. Schulz, “Westinghouse AP1000 advanced passive plant,” in Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP '03), Cordoba, Spain, May 2003.
[37]  “Westinghouse—AP1000,” Technology Fact Sheet, Westinghouse, 2008.
[38]  C. Ellis, A. Baxter, and A. Shenoy, “Modular helium reactor fuel cycle concepts and sustainability,” in Proceedings of the 2nd International Topical Meeting on High Temperature Reactor Technology (HTR '04), Beijing, China, September 2004.
[39]  “Design manual: CANDU 6 generating station physics design manual,” Wolsong NPP 2 3 4, 86-03310-DM-000 Rev. 1, Korea Atomic Energy Research Institute/Atomic Energy of Canada Limited, 1995.
[40]  J. J. Duderstadt and L. J. Hamilton, Nuclear Reactor Analysis, John Wiley & Sons, New York, NY, USA, 1976.
[41]  Y. Du and J. E. Parsons, “Update on the cost of nuclear power,” 09-004, Center for Energy and Environmental Policy Research, 2009.
[42]  “Cost estimating guidelines for Generation IV nuclear energy systems, Revision 4.2,” GIF/EMWG/2007/004, Generation IV International Forum, 2007.

Full-Text

Contact Us

service@oalib.com

QQ:3279437679

WhatsApp +8615387084133