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http://dx.doi.org/10.1016/j.net.2022.03.020

Neutronic design and evaluation of the solid microencapsulated fuel in LWR  

Deng, Qianliang (Institute of Nuclear and New Energy Technology, Tsinghua University)
Li, Songyang (Institute of Nuclear and New Energy Technology, Tsinghua University)
Wang, Dingqu (Institute of Nuclear and New Energy Technology, Tsinghua University)
Liu, Zhihong (Institute of Nuclear and New Energy Technology, Tsinghua University)
Xie, Fei (Institute of Nuclear and New Energy Technology, Tsinghua University)
Zhao, Jing (Institute of Nuclear and New Energy Technology, Tsinghua University)
Liang, Jingang (Institute of Nuclear and New Energy Technology, Tsinghua University)
Jiang, Yueyuan (Institute of Nuclear and New Energy Technology, Tsinghua University)
Publication Information
Nuclear Engineering and Technology / v.54, no.8, 2022 , pp. 3095-3105 More about this Journal
Abstract
Solid Microencapsulated Fuel (SMF) is a type of solid fuel rod design that disperses TRISO coated fuel particles directly into a kind of matrix. SMF is expected to provide improved performance because of the elimination of cladding tube and associated failure mechanisms. This study focused on the neutronics and some of the fuel cycle characteristics of SMF by using OpenMC. Two kinds of SMFs have been designed and evaluated - fuel particles dispersed into a silicon carbide matrix and fuel particles dispersed into a zirconium matrix. A 7×7 fuel assembly with increased rod diameter transformed from the standard NHR200-II 9×9 array was also introduced to increase the heavy metal inventory. A preliminary study of two kinds of burnable poisons (Erbia & Gadolinia) in two forms (BISO and QUADRISO particles) was also included. This study found that SMF requires about 12% enriched UN TRISO particles to match the cycle length of standard fuel when loaded in NHR200-II, which is about 7% for SMF with increased rod diameter. Feedback coefficients are less negative through the life of SMF than the reference. And it is estimated that the average center temperature of fuel kernel at fuel rod centerline is about 60 K below that of reference in this paper.
Keywords
Neutronics design; Accident tolerant fuel; Depletion analysis; Burnable poison;
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1 S. Pellegrino, L. Thome, A. Debelle, S. Miro, P. Trocellier, Radiation effects in carbides: TiC and ZrC versus SiC, Nucl. Instrum. Methods Phys. Res. Sect. B Beam Interact. Mater. Atoms 327 (2014) 103-107.   DOI
2 G.C. Silva, C.B. Yeamans, A.P. Sattelberger, T. Hartmann, G.S. Cerefice, K.R.J.I.c. Czerwinski, Reaction Sequence and Kinetics of Uranium Nitride Decomposition 48, 2009, pp. 10635-10642 (22).
3 K. Edsinger, Kurt Edsinger: EPRI and the Zero Fuel Failures Program, Nuclear News, 2010.
4 K.A. Terrani, J.O. Kiggans, L.L.J.J.o.n.m. Snead, Fabrication and Preliminary Evaluation of Metal Matrix Microencapsulated Fuels, 427, 2012, pp. 79-86, 1-3.
5 K.A. Terrani, J. Kiggans, Y. Katoh, K. Shimoda, F.C. Montgomery, B.L. Armstrong, C.M. Parish, T. Hinoki, J.D. Hunn, L.L.J.J.o.N.M. Snead, Fabrication and Characterization of Fully Ceramic Microencapsulated Fuels, 426, 2012, pp. 268-276, 1-3.
6 K.A. Terrani, C. Silva, J. Kiggans, Z. Cai, D. Shin, L.L.J.J.o.n.m. Snead, In Situ Ceramic Layer Growth on Coated Fuel Particles Dispersed in a Zirconium Metal Matrix, 437, 2013, pp. 171-177, 1-3.
7 W. Sun, X. Xiong, B.-y. Huang, G.-d. Li, H.-b. Zhang, Z.-k. Chen, X.-L. Zheng, ZrC ablation protective coating for carbon/carbon composites, Carbon 47 (14) (2009) 3368-3371.   DOI
8 Y. Katoh, S. Dong, A. Kohyama, Thermo-mechanical properties and microstructure of silicon carbide composites fabricated by nano-infiltrated transient eutectoid process, Fusion Eng. Des. 61 (2002) 723-731.   DOI
9 L.L. Snead, T. Nozawa, Y. Katoh, T.-S. Byun, S. Kondo, D.A.J.J.o.n.m. Petti, Handbook of SiC Properties for Fuel Performance Modeling, 371, 2007, pp. 329-377, 1-3.
10 Y. Katoh, L.L. Snead, I. Szlufarska, W.J. Weber, Radiation effects in SiC for nuclear structural applications, Curr. Opin. Solid State Mater. Sci. 16 (3) (2012) 143-152.   DOI
11 A.T. Motta, A. Couet, R.J. Comstock, Corrosion of zirconium alloys used for nuclear fuel cladding, Annu. Rev. Mater. Res. 45 (2015) 311-343.   DOI
12 J.J. Powers, B.D. Wirth, A review of TRISO fuel performance models, J. Nucl. Mater. 405 (1) (2010) 74-82.   DOI
13 L. Tan, T. Allen, E.J.J.o.N.M. Barringer, Effect of Microstructure on the Corrosion of CVD-SiC Exposed to Supercritical Water 394, 2009, pp. 95-101 (1).
14 W.J. Kim, H.S. Hwang, J.Y. Park, W.S. Ryu, Corrosion behaviors of sintered and chemically vapor deposited silicon carbide ceramics in water at 360 degrees C, J. Mater. Sci. Lett. 22 (8) (2003) 581-584.   DOI
15 K.A. Terrani, L.L. Snead, J.C.J.J.o.N.M. Gehin, Microencapsulated Fuel Technology for Commercial Light Water and Advanced Reactor Application, 427, 2012, pp. 209-224, 1-3.
16 H. Zhao, B. Liu, K. Zhang, C. Tang, Microstructure analysis of zirconium carbide layer on pyrocarbon-coated particles prepared by zirconium chloride vapor method, Nucl. Eng. Des. 251 (2012) 443-448.   DOI
17 N.E. Agency, State-of-the-Art Report on Light Water Reactor AccidentTolerant Fuels, 2018.
18 S.S. Raiman, C. Ang, P. Doyle, K.A. Terrani, Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings, in: 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017, August 13, 2017 - August 17, 2017, Springer International Publishing, Portland, OR, United states, 2018, pp. 259-267.
19 L. Snead, F. Venneri, Y. Kim, K. Terrani, J. Tulenko, C. Forsberg, P. Peterson, E.J.A.T. Lahoda, Fully Ceramic Microencapsulated Fuels: a Transformational Technology for Present and Next Generation Reactors, 2011.
20 J.J. Powers, W.J. Lee, F. Venneri, L.L. Snead, C. Jo, D. Hwang, J. Chun, Y. Kim, K.A.J.O.T. Terrani, O.R.N.L. KAERI/TR-/, K.A.E.R. Institute, Fully Ceramic Micro-encapsulated (FCM) Replacement Fuel for LWRs, 2013.
21 M.A. Pope, R.S. Sen, B. Boer, A.M. Ougouag, G. Youinou, Performance of Transuranic-Loaded Fully Ceramic Micro-encapsulated Fuel in LWRs Final Report, Including Void Reactivity Evaluation, Idaho National Laboratory (INL), 2011.
22 Y. Katoh, K.A.J.O.T. Terrani, Oak Ridge National Laboratory, Systematic Technology Evaluation Program for SiC/SiC Composite-Based Accident-Tolerant LWR Fuel Cladding and Core Structures: Revision 2015, 2015.
23 J.-Y. Park, I.-H. Kim, Y.-I. Jung, H.-G. Kim, D.-J. Park, W.-J. Kim, Long-term corrosion behavior of CVD SiC in 360 C water and 400 C steam, J. Nucl. Mater. 443 (1-3) (2013) 603-607.   DOI
24 C. Lorrette, C. Sauder, P. Billaud, C. Hossepied, G. Loupias, J. Braun, A. Michaux, E. Torres, F. Rebillat, J.J.P.o.t.T.F. Bischoff, SiC/SiC Composite Behavior in LWR Conditions and under High Temperature Steam Environment, 2015, pp. 126-134.
25 G.J. Youinou, R.S. Sen, Impact of accident-tolerant fuels and claddings on the overall fuel cycle: a preliminary systems analysis, Nucl. Technol. 188 (2) (2014) 123-138.   DOI
26 P. Malkki, The Manufacturing of Uranium Nitride for Possible Use in Light Water Reactors, KTH Royal Institute of Technology, 2015.
27 Z. Li, Y. Wang, J. Zhao, Z.J.A.o.N.E. Liu, Development of the Universe Based Geometry Criticality Search Capability in RMC and Analysis of NHR200-II Reactor, 134, 2019, pp. 401-413.
28 G. Giudicelli, Achievable Power Uprates in Pressurized Water Reactors Using Uranium Nitride Fuel, Massachusetts Institute of Technology, 2017.
29 L. Snead, K. Terrani, Y. Katoh, C. Silva, K. Leonard, A.J.J.o.N.M. Perez-Bergquist, Stability of SiC-matrix microencapsulated fuel constituents at relevant, LWR conditions 448 (1-3) (2014) 389-398.
30 K. Wang, Z. Li, D. She, Q. Xu, Y. Qiu, J. Yu, J. Sun, X. Fan, G. Yu, RMC-A Monte Carlo code for reactor core analysis, Ann. Nucl. Energy 82 (2015) 121-129.   DOI
31 M. Fratoni, K.A.J.T.o.t.A.N.S. Terrani, Metal Matrix Microencapsulated (M3) fuel neutronics performance in, PWRs 107 (2012) 1025.
32 D.G. Martin, Considerations pertaining to the achievement of high burn-ups in HTR fuel, Nucl. Eng. Des. 213 (2-3) (2002) 241-258.   DOI
33 A. Sajdova, Accident-tolerant Uranium Nitride, Chalmers University of Technology, 2017.
34 R.S. Sen, M.A. Pope, A.M. Ougouag, K.O.J.N.E. Pasamehmetoglu, Design, Assessment of Possible Cycle Lengths for Fully Encapsulated Microstructure Fueled Light Water Reactor Concepts, 255, 2013, pp. 310-320.
35 P.K. Romano, N.E. Horelik, B.R. Herman, A.G. Nelson, B. Forget, K. Smith, OpenMC: a state-of-the-art Monte Carlo code for research and development, Ann. Nucl. Energy 82 (2015) 90-97.   DOI
36 M. Fratoni, K.A.J.P.i.N.E. Terrani, PWR core design with metal matrix microencapsulated (M3), Fuel 100 (2017) 419-426.
37 J. Renier, Development of Improved Burnable Poisons for Commercial Nuclear Power Reactors, ORNL Oak Ridge National Laboratory (United States). Funding organisation, US, 2002.
38 P. Phelps, in: Heat Transfer and Fluid Flow in Nuclear Systems: Henri Fenech, Pergamon Press, Oxford, 1981, p. 582. Pergamon, 1984.
39 D.R. Olander, Fundamental Aspects of Nuclear Reactor Fuel Elements: Solutions to Problems, California Univ., Berkeley (USA), 1976. Dept. of Nuclear Engineering.
40 W. Jodrey, E. Tory, Computer simulation of close random packing of equal spheres, Phys. Rev. 32 (4) (1985) 2347.   DOI
41 N.E. Todreas, M.S. Kazimi, Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, CRC press .
42 D. Kim, H.-G. Lee, Y. Park, J.-Y. Park, W.-J. Kim, Effect of dissolved hydrogen on the corrosion behavior of chemically vapor deposited SiC in a simulated pressurized water reactor environment, Corrosion Sci. 98 (2015) 304-309.   DOI
43 M.A. Pope, R.S. Sen, A.M. Ougouag, G. Youinou, B.J.N.e. Boer, design, Neutronic analysis of the burning of transuranics in fully ceramic micro-encapsulated tri-isotropic particle-fuel in a, PWR 252 (2012) 215-225.