Acknowledgement
This work is supported by the National Key R&D Program of China (2018YFE0180900).
References
- M. Williams, Perturbation theory for nuclear reactor analysis, in: CRC Handbook of Nuclear Reactor Calculations, vol. 3, 1986, pp. 63-188.
- T. Drzewiecki, Adjoint Based Uncertainty Quantification and Sensitivity Analysis for Nuclear Thermal-Fluids Codes, Doctoral thesis, the University of Michigan, 2013.
- A.T. Godfrey, VERA Core Physics Benchmark Progression Problem Specifications, Revision 4, CASL, 2014. Tech. Rep. CASL-U-2012-0131-004.
- R. Ferrer, J. Rhodes, Implementation and Verification of a Transport-Based Adjoint Capability in CASMO5, PHYSOR, Cancun, Mexico, 2018. April 22-26, 2018.
- F. Li, Z. Luo, Adjoint calculation of diffusion-difference equation with discontinuity factor theory, Nucl. Power Eng. v19 (6) (1998) 485-489.
- A. Zhu, Y. Xu, T. Downar, The implementation and analysis of the MOC and CMFD adjoint capabilities in the 2D-1D code MPACT, in: Proc. M&C 2015, Nashville, TN, USA, 2015.
- B.C. Yee, B. Kochunas, E.W. Larsen, A multilevel in space and energy solver for multigroup diffusion eigenvalue problems, Nucl. Eng. Technol. v49 (2017) 1125-1134. https://doi.org/10.1016/j.net.2017.07.014
- Y. Xu, C. Hao, A novel and efficient hybrid RSILU preconditioner for the parallel GMRES solution of the coarse mesh finite difference equations for practical reactor simulations, Nucl. Sci. Eng. v194 (2020) 104-119. https://doi.org/10.1080/00295639.2019.1657322
- C. Hao, L. Kang, Y. Xu, et al., 3D whole-core neutron transport simulation using 2D/1D method via multi-level generalized equivalence theory based CMFD acceleration, Ann. Nucl. Energy v122 (2018) 79-90. https://doi.org/10.1016/j.anucene.2018.08.014
- M.A. Smith, E.E. Lewis, B.C. Na, Benchmark on Deterministic Transport Calculations without Spatial Homogenization: MOX Fuel Assembly 3-D Extension Case, Organization for Economic Co-operation and Development/Nuclear Energy Agency, 2005.
- A.T. Godfrey, VERA Core Physics Benchmark Progression Problem Specifications, Revision 4, CASL, 2014. Tech. Rep. CASL-U-2012-0131-004.
- X. Shang, G. Shi, K. Wang, One step method for multigroup Adjoint neutron flux through continuous energy Monte Carlo calculation, in: The 26th International Conference on Nuclear Engineering, July 22-26, 2018 (London, England).
Cited by
- Discrete element-embedded finite element model for simulation of soft particle motion and deformation vol.68, 2021, https://doi.org/10.1016/j.partic.2021.10.008