A new high-fidelity neutronics code NECP-X

Abstract The high-fidelity reactor physics calculation attracts a lot of attention because of the development of high performance computing technology and increasing requirement of reducing the approximation of traditional methods. Here introduces a new high-fidelity deterministic neutronics code NECP-X being developed at Nuclear Engineering Computational Physics (NECP) lab at Xi’an Jiaotong University. Compared to previous developed codes like DeCART, MPACT and nTRACER, it has its own separate features such as a pseudo-resonant-nuclide subgroup method, a new free-matrix CMFD acceleration method and an axial SN solver for improving accuracy, etc. The VERA progression problems 1 through 5-2D are tested to verify NECP-X, and the numerical results show that NECP-X can obtain accurate results for all of this verification problems.

[1]  Liangzhi Cao,et al.  Improved resonance calculation of fluoride salt-cooled high-temperature reactor based on subgroup method , 2016 .

[2]  Brendan Kochunas,et al.  Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT , 2016, J. Comput. Phys..

[3]  A. Yamamoto,et al.  Derivation of Optimum Polar Angle Quadrature Set for the Method of Characteristics Based on Approximation Error for the Bickley Function , 2007 .

[4]  Han Gyu Joo,et al.  Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code , 2015 .

[5]  Han Gyu Joo,et al.  Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers , 2013 .

[6]  Hongchun Wu,et al.  Resonance Elastic Scattering and Interference Effects Treatments in Subgroup Method , 2016 .

[7]  Dorothea Wiarda,et al.  Development of a New 47-Group Library for the CASL Neutronics Simulators , 2015 .

[8]  Brendan Kochunas,et al.  Improvement of transport-corrected scattering stability and performance using a Jacobi inscatter algorithm for 2D-MOC , 2017 .

[9]  Chen Zhao,et al.  Development and verification of the high-fidelity neutronics and thermal-hydraulic coupling code system NECP-X/SUBSC , 2018 .

[10]  Gang Wang,et al.  Analysis of BEAVRS two-cycle benchmark using RMC based on full core detailed model , 2017 .

[11]  N. Isaev,et al.  The method of subgroups for considering the resonance structure of the cross sections in neutron calculations (part 1) , 1970 .

[12]  Alain Hébert The Ribon Extended Self-Shielding Model , 2005 .

[13]  N. Z. Cho,et al.  Fusion of method of characteristics and nodal method for 3-D whole-core transport calculation , 2002 .

[14]  Rafael Macian-Juan,et al.  High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW , 2015 .

[15]  Liangzhi Cao,et al.  A new three-dimensional method of characteristics for the neutron transport calculation , 2011 .

[16]  Liangzhi Cao,et al.  Improvements of the subgroup resonance calculation code SUGAR , 2014 .

[17]  Kord Smith,et al.  Impact of inflow transport approximation on light water reactor analysis , 2015, J. Comput. Phys..

[18]  W. Yang,et al.  Heterogeneous Pseudo-Resonant Isotope Method for Resolved Resonance Interference Treatment in Resonance Self-Shielding Calculation , 2016 .

[19]  A. Yamamoto,et al.  Evaluation of Dancoff Factors in Complicated Geometry using the Method of Characteristics , 2006 .

[20]  Youqi Zheng,et al.  Leakage reconstruction method for 2D/1D fusion transport calculations , 2017 .

[21]  F. Leszczynski,et al.  Neutron resonance treatment with details in space and energy for pin cells and rod clusters , 1987 .

[22]  Hongchun Wu,et al.  The pseudo-resonant-nuclide subgroup method based global–local self-shielding calculation scheme , 2018 .