A Variational Nodal Approach to 2D/1D Pin Resolved Neutron Transport for Pressurized Water Reactors
- Xi'an Jiaotong Univ., Xi'an, Shannxi (China)
- Northwestern Univ., Evanston, IL (United States)
- Argonne National Lab. (ANL), Lemont, IL (United States)
- Purdue Univ., West Lafayette, IN (United States)
A two-dimensional/one-dimensional (2D/1D) variational nodal approach is presented for pressurized water reactor core calculations without fuel-moderator homogenization. A 2D/1D approximation to the within-group neutron transport equation is derived and converted to an even-parity form. The corresponding nodal functional is presented and discretized to obtain response matrix equations. Within the nodes, finite elements in the x-y plane and orthogonal functions in z are used to approximate the spatial flux distribution. On the radial interfaces, orthogonal polynomials are employed; on the axial interfaces, piecewise constants corresponding to the finite elements eliminate the interface homogenization that has been a challenge for method of characteristics (MOC)-based 2D/1D approximations. The angular discretization utilizes an even-parity integral method within the nodes, and low-order spherical harmonics (PN) on the axial interfaces. The x-y surfaces are treated with high-order PN combined with quasi-reflected interface conditions. Furthermore, the method is applied to the C5G7 benchmark problems and compared to Monte Carlo reference calculations.
- Research Organization:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC), Basic Energy Sciences (BES); National Natural Science Foundation of China (NSFC)
- Grant/Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1374150
- Journal Information:
- Nuclear Science and Engineering, Vol. 186, Issue 2; ISSN 0029-5639
- Publisher:
- American Nuclear Society - Taylor & FrancisCopyright Statement
- Country of Publication:
- United States
- Language:
- English
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