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Modeling and simulation challenges pursued by the consortium for advanced simulation of light water reactors (CASL). (English) Zbl 1349.82173
Summary: The Consortium for the Advanced Simulation of Light Water Reactors (CASL), the first Energy Innovation Hub of the Department of Energy, was established in 2010 with the goal of providing modeling and simulation (M&S) capabilities that support and accelerate the improvement of nuclear energy’s economic competitiveness and the reduction of spent nuclear fuel volume per unit energy, and all while assuring nuclear safety. To accomplish this requires advances in M&S capabilities in radiation transport, thermal-hydraulics, fuel performance and corrosion chemistry. To focus CASL’s R&D, industry challenge problems have been defined, which equate with long standing issues of the nuclear power industry that M&S can assist in addressing. To date CASL has developed a multi-physics “core simulator” based upon pin-resolved radiation transport and subchannel (within fuel assembly) thermal-hydraulics, capitalizing on the capabilities of high performance computing. CASL’s fuel performance M&S capability can also be optionally integrated into the core simulator, yielding a coupled multi-physics capability with untapped predictive potential. Material models have been developed to enhance predictive capabilities of fuel clad creep and growth, along with deeper understanding of zirconium alloy clad oxidation and hydrogen pickup. Understanding of corrosion chemistry (e. G., CRUD formation) has evolved at all scales: micro, meso and macro. CFD R&D has focused on improvement in closure models for subcooled boiling and bubbly flow, and the formulation of robust numerical solution algorithms. For multiphysics integration, several iterative acceleration methods have been assessed, illuminating areas where further research is needed. Finally, uncertainty quantification and data assimilation techniques, based upon sampling approaches, have been made more feasible for practicing nuclear engineers via R&D on dimensional reduction and biased sampling. Industry adoption of CASL’s evolving M&S capabilities, which is in progress, will assist in addressing long-standing and future operational and safety challenges of the nuclear industry.
MSC:
82D75 Nuclear reactor theory; neutron transport
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[1] What are the energy innovation hubs?, energy.gov site, (2010)
[2] Collins, Benjamin; Stimpson, Shane; Kelley, Blake W.; Young, Mitchell T. H.; Kochunas, Brendan; Larsen, Edward W.; Downar, Thomas; Godfrey, Andrew, Three-dimensional nuclear reactor core simulations of the Boltzmann transport equation with the 2D/1D method using MPACT, J. Comput. Phys., (2016), in this issue
[3] Croff, A. G., ORIGEN2: a versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials, Nucl. Technol., 62, 335, (1983)
[4] Salko, Robert K.; Avramova, Maria N., CTF theory manual, (November 2014), Pennsylvania State University
[5] Turner, J.; Summers, R.; Sieger, M., The virtual environment for reactor applications (VERA): design and architecture, J. Comput. Phys., (2016), in this issue
[6] Hamilton, Steven P.; Evans, Thomas M.; Davidson, Gregory G.; Johnson, Seth R.; Pandya, Tara M.; Godfrey, Andrew T., Hot zero power reactor calculations using the insilico code, J. Comput. Phys., (2016), in press · Zbl 1349.82086
[7] Pandya, Tara M.; Johnson, Seth R.; Evans, Thomas M.; Davidson, Gregory G.; Hamilton, Steven P.; Godfrey, Andrew T., Implementation, capabilities, and benchmarking of shift, a massively parallel Monte Carlo radiation transport code, J. Comput. Phys., 308, 239-272, (2016) · Zbl 1351.82083
[8] Deshon, J.; Hussey, D.; Kendrick, B.; McGurk, J.; Secker, J.; Short, M., Pressurized water reactor fuel crud and corrosion modeling, JOM, 63, 8, 64-72, (2011)
[9] Kendrick, B.; Stanek, C.; Short, M., MAMBA (MPO advanced model for boron analysis), development for CASL: update and applications, (2014), presented at the EPRI-PTAC Meeting, San Antonio, TX, retrieved from
[10] Jin, Miaomiao; Short, Michael, Multiphysics modeling of two-phase film boiling within porous corrosion deposits (CRUD), J. Comput. Phys., (2016), in this issue · Zbl 1349.76224
[11] Christon, Mark A.; Bakosi, Jozsef; Nadiga, Balu; Berndt, Markus; Francois, Marianne M.; Stagg, Alan K.; Xia, Yidong; Luo, Hong, A hybrid incremental projection method for thermal-hydraulics application, J. Comput. Phys., (2016), in this issue · Zbl 1349.76190
[12] Aleshin, Y.; Beard, C.; Mangham, G.; Mitchell, D.; Malek, E.; Young, M., The effect of Pellet and local power variations on PCI margin, (Proceedings of Top Fuel, 2010, Orlando, (2010)), Paper 41
[13] Montgomery, R.; Sunderland, D.; Stanek, C.; Wirth, B.; Capps, N.; Williamson, R., Peregrine: advanced modeling of Pellet-cladding interaction (PCI) failure in lwrs, (Proceedings of the TopFuel 2012 Reactor Fuel Performance Meeting, Manchester, UK, (2012))
[14] Hales, J. D.; Williamson, R. L.; Novascone, S. R.; Pastore, G.; Spencer, B. W.; Stafford, D. S.; Gamble, K. A.; Perez, D. M.; Liu, W., BISON theory manual—the equations behind nuclear fuel analysis, (October 2014), BISON Release 1.1, INL/EXT-13-29930, Rev. 1
[15] Montgomery, Robert; Toḿe, Carlos; Liu Alankar, Wenfeng; Subramanian, Gopinath; Stanek, Chris, Use of multiscale zirconium alloy deformation models in nuclear fuel behavior analysis, J. Comput. Phys., (2016), in this issue
[16] Clarno, Kevin; Pawlowski, Roger, Incorporate MPACT into TIAMAT and demonstrate Pellet-clad interaction (PCI) calculations, (2014), CASL milestone report: L3:PHI.CMD.P10.01
[17] Rashid, J.; Yagnik, S.; Montgomery, R., Light water reactor fuel performance modeling and multi-dimensional simulation, JOM, 63, 8, 81-88, (2011)
[18] Lu, R.; Karoutas, Z.; Sham, T., CASL virtual reactor predictive simulation: grid-to-rod fretting wear, JOM, 63, 8, 53-58, (2011)
[19] Christon, Mark A.; Lu, Roger; Bakosi, Jozsef; Nadig, Balu; Karoutas, Zeses; Berndt, Markus, Large-eddy simulation, fuel rod vibration and grid-to-rod fretting, J. Comput. Phys., (2016), in this issue · Zbl 1351.76035
[20] Fang, Jun; Mishra, V.; Bolotnov, Igor A., Interface tracking simulation of two-phase bubbly flow in a PWR subchannel, (International Embedded Topical Meeting on Advances in Thermal Hydraulics, ATH’ 14, Reno, NV, (2014))
[21] Ott, K. O.; Neuhold, R. J., Introduction to nuclear reactor dynamics, (1985), American Nuclear Society La Grange Park, IL
[22] Montgomery, R., Industry information to support interim RIA criteria, public workshop on interim RIA criteria, (9 November 2006), US NRC report ML063190105
[23] Raynauad, R., Fuel fragmentation, relocation, and dispersal during the loss-of-coolant A, (March 2012), US NRC report NUREG-2121
[24] Lewis, Allison; Smith, Ralph; Williams, Brian; Figueroa, Victor, An information theoretic approach to use high-fidelity codes to calibrate low-fidelity codes, J. Comput. Phys., (2016), in this issue · Zbl 1360.62416
[25] Rider, William; Witkowski, Walt; Kamm, James R.; Wildey, Tim, Robust verification analysis, J. Comput. Phys., 307, 146-163, (2016) · Zbl 1352.65137
[26] Adams, B.; Bauman, L.; Bohnhoff, W.; Dalbey, K.; Eddy, J.; Ebeida, M.; Eldred, M.; Hough, P.; Hu, K.; Jakeman, J.; Swiler, L.; Vigil, D., DAKOTA: a multilevel parallel object-oriented framework for design optimization, parameter estimation, uncertainty quantification, and sensitivity analysis: version 5.3.1 User’s manual, (May 2013), SNL SAND report
[27] Shadid, J. N.; Smith, T. M.; Cyr, E. C.; Wildey, T. M.; Pawlowski, R. P., Stabilized FE simulation of prototype thermal-hydraulics problems with integrated adjoint-based capabilities, J. Comput. Phys., (2016), in this issue · Zbl 1349.76266
[28] Godfrey, A.; Collins, B.; Kim, K. S.; Lee, J.; Powers, J.; Salko, R.; Stimpson, S.; Wieselquist, W.; Montgomery, R.; Montgomery, R.; Kochunas, B.; Jabaay, D.; Capps, N.; Secker, J., VERA benchmarking results for Watts bar nuclear plant unit 1 cycles 1-12, (2015), CASL milestone report: CASL-U-2015-0206-000
[29] Rak, Z.; O’Brien, C. J.; Shin, D.; Andersson, A. D.; Stanek, C. R.; Brenner, D. W., Theoretical assessment of bonaccordite formation in pressurized water reactors, J. Nucl. Mater., (2016), in press
[30] Baglietto, E.; Gilman, L.; Sugrue, R., Advanced subgrid modeling for multiphase CFD in CASL VERA tools, (Proc. 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety, Okinawa, Japan, (December 2014))
[31] Fang, A. M.; Fang, J.; Feng, J. Y.; Bolotnov, I. A., Estimation of sheer-induced lift force in laminar flow and turbulent flows, Nucl. Technol., 190, 3, 274-291, (2015)
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