1 |
Y.-A. Chao, A new and rigorous theoryePart III: a succinct summary of the theory, the equivalent and implementation issues, Ann. Nucl. Energy 119 (2018) 310-321.
DOI
|
2 |
Y.-A. Chao, A new and rigorous theory for piecewise homogeneous regions, Ann. Nucl. Energy 96 (2016) 112-125.
DOI
|
3 |
Y.-A. Chao, A new and rigorous theorye Part II: generalization to , Ann. Nucl. Energy 110 (2017) 1176-1196.
DOI
|
4 |
A. Cherezov, R. Sanchez, H.G. Joo, A reduced-basis element method for pin-bypin reactor core calculations in diffusion and approximations, Ann. Nucl. Energy 116 (2018) 195-209.
DOI
|
5 |
C. Zhang, G. Chen, Fast solution of neutron transport equation by reduced basis finite element method, Ann. Nucl. Energy 120 (2018) 707-714.
DOI
|
6 |
T.-Y. Lin, Y.-W.H. Liu, A next generation method for light water reactor core analysis by using global/local iteration method with , Ann. Nucl. Energy 118 (2018) 49-60.
DOI
|
7 |
W. Yang, H. Wu, Y. Li, L. Cao, S. Wang, Acceleration of the exponential function expansion nodal method by multi-group GMRES algorithm for PWR pinby-pin calculation, Ann. Nucl. Energy 120 (2018) 869-879.
DOI
|
8 |
T. Downar, D. Lee, Y. Xu, T. Kozlowski, User and Theory Manual for the PARCS Neutronics Core Simulator (U.S. NRC Core Neutronics Simulator), School of Nuclear Engineering Purdue University, 2004.
|
9 |
M. Tatsumi, A. Yamamoto, Advanced PWR core calculation based on multigroup nodal-transport method in three-dimensional pin-by-pin geometry, J. Nucl. Sci. Technol. 40 (2003) 376-387.
DOI
|
10 |
Y.A. Chao, A Theoretical Analysis of the Coarse Mesh Finite Fifference Representation in Advanced Nodal Methods. Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Senda Ed., 1999, pp. 117-126. Madrid.
|
11 |
J.M. Aragones, C. Ahnert, N. Garcia-Herranz, The analytic coarse mesh finite difference method for multigroup and multidimensional diffusion calculations, Nucl. Sci. Eng. 157 (2007) 1-15.
|
12 |
J.-A. Lozano, N. Garcia-Herranz, C. Ahnert, J.-M. Aragones, The analytic nodal diffusion solver ANDES in multigroups for 3D rectangular geometry: development and performance analysis, Ann. Nucl. Energy 35 (2008) 2365-2374.
DOI
|
13 |
M.U.s. Manual, Version 2.7. 0, Los Alamos National Laboratory, Los Alamos (NM), 2011.
|
14 |
B. Cho, J.H. Won, N.Z. Cho, Analytic function expansion nodal(AFEN) method extended to multigroup simplified (SP3) equations via partial current moment transformation, Trans. Am. Nucl. Soc. 103 (2011) 714-717.
|
15 |
M. Capilla, D. Ginestar, G. Verdu, Applications of the multidimensional equations to complex fuel assembly problems, Ann. Nucl. Energy 36 (2009) 1624-1634.
DOI
|
16 |
OECD/NEA, Benchmark on Deterministic Transport Calculations without Spatial Homogenisation: a 2-D/3-D MOX Fuel Assembly Benchmark. NEA/NSA/DOC(2003)16, 2003.
|
17 |
Argonne Code Center, ANL Benchmark Book-Report ANL-7416, Argonne National Laboratory, Argonne, IL, 1977.
|
18 |
T. Bahadir, S. Lindahl, S.P. Palmtag, SIMULATE-4 multi-group nodal code with microscopic depletion model, in: American Nuclear Society Topical Meeting in Mathematics and Computations, Avignon, France, 2005.
|
19 |
T. Takeda, H. Ikeda, 3-D neutron transport benchmarks, J. Nucl. Sci. Technol. 28 (1991) 656-669.
DOI
|
20 |
E.H. Ryu, H.G. Joo, Finite element method solution of the simplified equations for general geometry applications, Ann. Nucl. Energy 56 (2013) 194-207.
DOI
|
21 |
P. Kotiluoto, Adaptive Tree Multigrids and Simplified Spherical Harmonics Approximation in Deterministic Neutral and Charged Particle Transport, VTT Publications, 2007.
|
22 |
S.A. Thompson, Advanced Reactor Physics Methods for Heterogeneous Reactor Cores, The pennsylvania state university college of engineering, 2014.
|
23 |
A. Henry, Nuclear-Reactor Analysis, second ed., MIT Press, 1980.
|
24 |
A. Hebert, Mixed-dual implementations of the simplified Pn method, Ann. Nucl. Energy 37 (2010) 498-511.
DOI
|
25 |
G. Longoni, A. Haghighat, The even-parity simplified SN equations applied to a MOX fuel assembly benchmark problem on distributed memory environments. PHYSOR 2004-the physics of fuel cycles and advanced nuclear systems, Global Developments (2004) 25-29.
|
26 |
A. Vidal-Ferrandiz, S. Gonzalez-Pintor, D. Ginestar, C. Demaziere, G. Verdu, Pin-wise homogenization for neutron transport approximation using the finite element method, J. Comput. Appl. Math. 330 (2017) 806-821.
DOI
|
27 |
C. Beckert, U. Grundmann, Development and verification of a nodal approach for solving the multigroup S equations, Ann. Nucl. Energy 35 (2008) 75-86.
DOI
|
28 |
M.H.J. Bahabadi, A. Pazirandeh, M. Athari, New analytic function expansion nodal (AFEN) method for solving multigroup neutron simplified (S) equations, Ann. Nucl. Energy 77 (2015) 148-160.
DOI
|