316
Views
4
CrossRef citations to date
0
Altmetric
Technical Papers

Improved Accuracy in the 2-D/1-D Method with Anisotropic Transverse Leakage and Cross-Section Homogenization

ORCID Icon, ORCID Icon, ORCID Icon & ORCID Icon
Pages 219-239 | Received 07 Jun 2018, Accepted 29 Jul 2018, Published online: 19 Sep 2018

References

  • B. KELLEY and E. LARSEN, “2D/1D Approximations to the 3D Neutron Transport Equation. I: Theory,” Proc. Mathematics and Computational Methods (M&C 2013), Sun Valley, Idaho, May 5–9, 2013, American Nuclear Society (2013).
  • B. COLLINS et al., “Stability and Accuracy of 3D Neutron Transport Simulations Using the 2D/1D Method in MPACT,” J. Comput. Phys., 326, 612 (2016); https://doi.org/10.1016/j.jcp.2016.08.022.
  • T. DOWNAR, B. KOCHUNAS, and B. COLLINS, “Validation and Verification of the MPACT Code,” Proc. PHYSOR 2016, Sun Valley, Idaho, May 1–5, 2016, American Nuclear Society (2016).
  • J. ASKEW, “A Characteristics Formulation of the Neutron Transport Equation in Complicated Geometry,” AEEW-M 1108, United Kingdom Atomic Energy Authority, Winfirth (1972).
  • K. SMITH, “Nodal Method Storage Reduction by Nonlinear Iteration,” Trans. Am. Nucl. Soc., 44, 265 (1983).
  • H. JOO et al., “Methods and Performance of a Three-Dimensional Whole Core Transport Code DeCART,” Proc. PHYSOR 2004, Chicago, Illinois, April 25–29, 2004, American Nuclear Society (2004).
  • J. CHO et al., “Axial SPN and Radial MOC Coupled Whole Core Transport Calculation,” J. Nucl. Sci. Technol., 44, 1156 (2007); https://doi.org/10.1080/18811248.2007.9711359.
  • N. CHO, G. LEE, and C. PARK, “Fusion of Method of Characteristics and Nodal Method for 3-D Whole-Core Transport Calculation,” Trans. Am. Nucl. Soc., 86, 322 (2002).
  • N. CHO, G. LEE, and C. PARK, “Refinement of the 2-D/1-D Fusion Method for 3-D Whole-Core Transport Calculation,” Trans. Am. Nucl. Soc., 87, 417 (2002).
  • G. LEE and N. CHO, “2D/1D Fusion Method Solutions of the Three-Dimensional Transport OECD Benchmark Problem C5G7 MOX,” Prog. Nucl. Energy, 48, 410 (2006); https://doi.org/10.1016/j.pnucene.2006.01.010.
  • S. YUK and N. Z. CHO, “Whole-Core Transport Solutions with 2-D/1-D Fusion Kernel via p-CMFD Acceleration and p-CMFD Embedding of Nonoverlapping Local/Global Iterations,” Nucl. Sci. Eng., 181, 1, 1 (2015); https://doi.org/10.13182/NSE14-88.
  • S. YUK and N. CHO, “Comparison of 1-D/1-D Fusion Method and 1-D/1-D Hybrid Method in Two-Dimensional Neutron Transport Problems: Convergence Analysis and Numerical Results,” Nucl. Sci. Eng., 184, 151 (2016); https://doi.org/10.13182/NSE15-128.
  • S. STIMPSON, “An Azimuthal, Fourier Moment-Based Axial SN Solver for the 2D/1D Scheme,” PhD Thesis, University of Michigan (2015).
  • S. STIMPSON, B. COLLINS, and T. DOWNAR, “A 2-D/1-D Transverse Leakage Approximation Based on Azimuthal, Fourier Moments,” Nucl. Sci. Eng., 185, 243 (2017); https://doi.org/10.1080/00295639.2016.1272360.
  • M. JARRETT et al., “Progress in Characterizing 2D/1D Accuracy in MPACT,” Proc. Mathematics & Computational Methods (M&C 2017), Jeju, Korea, 2017.
  • T. ZHANG et al., “Assessment of 2D-Transport/1D-Diffusion Approximations in a Pin Resolved Variational Nodal Method for PWR Calculations,” Proc. Mathematics & Computational Methods (M&C 2017), Jeju, Korea, 2017.
  • T. ZHANG et al., “A Variational Nodal Approach to 2D/1D Pin Resolved Neutron Transport for Pressurized Water Reactors,” Nucl. Sci. Eng., 186, 120 (2017); https://doi.org/10.1080/00295639.2016.1273023.
  • E. LEWIS, M. SMITH, and B. NA, “Benchmark on Deterministic 3-D MOX Fuel Assembly Transport Calculations Without Spatial Homogenization,” Prog. Nucl. Energy, 48, 381 (2006); https://doi.org/10.1016/j.pnucene.2006.01.001.
  • F. FINNEMANN and M. WAGNER, “Interface Nodal Current Technique for Multi-Dimensional Reactor Calculation,” Atomkernenergie, 30, 123 (1977).
  • G. GIUDICELLI, K. SMITH, and B. FORGET, “Generalized Equivalence Methods for 3D Multi-Group Neutron Transport,” Ann. Nucl. Energy, 112, 9 (2018); https://doi.org/10.1016/j.anucene.2017.09.024.
  • T. TAKEDA and H. IKEDA, “Final Report on the 3-D Neutron Transport Benchmarks,” AEEW-M 1008, Organisation for Economic Co-operation and Development/Nuclear Energy Agency (1991).
  • K. SMITH and B. FORGET, “Challenges in the Development of High-Fidelity LWR Core Neutronics Tools,” Proc. Mathematics and Computational Methods (M&C 2013), Sun Valley, Idaho, May 5–9, 2013, American Nuclear Society (2013).
  • S. SHANER et al., “Verification of the 3D Method of Characteristics Solver in OpenMOC,” Proc. PHYSOR 2016, Sun Valley, Idaho, May 1–5, 2016, American Nuclear Society (2016).
  • T. PANDYA et al., “SHIFT: A Massively Parallel Monte Carlo Radiation Transport Package,” Proc. Mathematics and Computational Methods (M&C 2015), Nashville, Tennessee, April 19–23, 2015, American Nuclear Society (2015).

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.