387
Views
26
CrossRef citations to date
0
Altmetric
Technical Papers

A Three-Dimensional Variational Nodal Method for Pin-Resolved Neutron Transport Analysis of Pressurized Water Reactors

, , , , &
Pages 160-174 | Received 10 May 2017, Accepted 29 Jun 2017, Published online: 07 Aug 2017

References

  • R. ROY, “Reactor Core Methods,” Nuclear Computational Science, a Century in Review, Y. AZMY and E. SARTORES, Eds., Springer, New York (2010).
  • H. G. 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) (CD-ROM).
  • N. Z. CHO and G. S. LEE, “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.
  • B. KOCKUNAS et al., “Overview of Development and Design of MPACT: Michigan Parallel Characteristics Transport Code,” Proc. M&C 2013, Sun Valley, Idaho, May 5–9, 2013.
  • J.-Y. 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.
  • M. HURSIN et al., “The Development and Implementation of a One-Dimensional Sn Method in the 2D/1D Integral Transport Solution,” Nucl. Sci. Eng., 176, 186 (2014); https://doi.org/10.13182/NSE12-4.
  • 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 (2015); https://doi.org/10.13182/NSE14-88.
  • J. Y. CHO and H. G. JOO, “Solution of the C5G7 MOX Benchmark Three-Dimensional Extension Problems by the DeCART Direct Whole Core Calculation Code,” Prog. Nucl. Energy, 48, 456 (2006); https://doi.org/10.1016/j.pnucene.2006.01.006.
  • B. KOCHUNAS, “A Hybrid Parallel Algorithm for the 3-D Method of Characteristics Solution of the Boltzmann Transport Equation on High Performance Compute Clusters,” PhD Dissertation, University of Michigan (2013).
  • A. MARIN-LAFLECHE, M. A. SMITH, and C. H. LEE, “PROTEUS-MOC: A 3-D Deterministic Solver Incorporating 2-D Method of Characteristics,” Proc. Int. Conf. Mathematics, Computational Methods & Reactor Physics (M&C2013), Sun Valley, Idaho, May 5–8, 2013.
  • Y. S. JUNG and W. S. YANG, “A Consistent CMFD Formulation for the Acceleration of Neutron Transport Calculations Based on the Finite Element Method,” Nucl. Sci. Eng., 185, 307 (2017); https://doi.org/10.1080/00295639.2016.1272369.
  • G. GUNOW et al., “Accuracy and Performance of 3D MOC for Full-Core PWR Problems,” Proc. M&C 2017, Jeju, Korea, April 16–20, 2017.
  • S. SAMUEL et al., “Verification of the 3D Method of Characteristics Solver in OpenMOC,” Proc. PHYSOR 2016, Sun Valley, Idaho, May 1, 2016.
  • C. B. CARRICO, E. E. LEWIS, and G. PALMIOTTI, “Three Dimensional Variational Nodal Transport Methods for Cartesian, Triangular and Hexagonal Criticality Calculations,” Nucl. Sci. Eng., 111, 168 (1992); https://doi.org/10.13182/NSE92-1.
  • E. E. LEWIS, C. B. CARRICO, and G. PALMIOTTI, “Variational Nodal Formulation for the Spherical Harmonics Equations,” Nucl. Sci. Eng., 122, 194 (1996); https://doi.org/10.13182/NSE96-1.
  • M. A. SMITH, E. E. LEWIS, and E. R. SHEMON, “DIF3D-VARIANT 11.0: A Decade of Updates,” ANL/NE-14/1, Argonne National Laboratory (Jan. 2014).
  • M. A. SMITH et al., “A Finite Subelement Generalization of the Variational Nodal Method,” Nucl. Sci. Eng., 144, 36 (2003); https://doi.org/10.13182/NSE144-36.
  • M. A. SMITH et al., “An Integral Form of the Variational Nodal Method,” Nucl. Sci. Eng., 146, 141 (2004); https://doi.org/10.13182/NSE146-141.
  • E. E. LEWIS, M. A. SMITH, and G. PALMIOTTI, “A New Paradigm for Local-Global Coupling in Whole-Core Neutron Transport,” Nucl. Sci. Eng., 161, 927 (2009); https://doi.org/10.13182/NSE161-279.
  • E. E. LEWIS and M. A. SMITH, “Comparison of Homogenized and Enhanced Diffusion Solutions of Model PWR Problems,” Proc. PHYSOR 2012—Advances in Reactor Physics—Linking research, Industry, and Education, Knoxville, Tennessee, April 15–20, 2012.
  • T. ZHANG et al., “A Variational Nodal Approach to 2D/1D Pin-Resolved Neutron Transport: I Diffusion Theory,” Trans. Am. Nucl. Soc., 114, 770 (2016).
  • T. ZHANG et al., “Variational Nodal 2D/1D Transport/Diffusion Solutions of the C5G7 Benchmark Problems,” Trans. Am. Nucl. Soc., 115, 1118 (2016).
  • 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.
  • T. ZHANG et al., “Assessment of 2D-Transport/1D-Diffusion Approximations in a Pin Resolved Variational Nodal Method for PWR Calculations,” Proc. M&C 2017, Jeju, Korea, April 16-20, 2017.
  • M. A. SMITH, E. E. LEWIS, and B. C. NA, “Benchmark on Deterministic Transport Calculations without Spatial Homogenization: A 2-D/3-D MOX Fuel Assembly 3-D Benchmark,” NEA/NSC/DOC (2003).
  • 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.

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.