Exponential Function Expansion Nodal Diffusion Method

Author(s):  
Yunzhao Li ◽  
Hongchun Wu ◽  
Liangzhi Cao ◽  
Qichang Chen

An exponential function expansion nodal diffusion method is proposed to take care of diffusion calculation in unstructured geometry. Transverse integral technique is widely used in nodal method in regular geometry, such as rectangular and hexagonal, while improper in arbitrary triangular geometry because of the mathematical singularity. In this paper, nodal response matrix is derived by expanding detailed nodal flux distribution into a sum of exponential functions, and nodal balance equation can be obtained by strict integral in the polygonal node. Numerical results illustrate that the exponential function expansion nodal method in rectangular and triangular block can solve neutron diffusion equation in regular and irregular geometry.

Author(s):  
Pan Qingquan ◽  
Lu Haoliang ◽  
Li Dongsheng ◽  
Wang Kan

Solving the SP3 equation is the key technology of the Next Generation Reactor Physics Calculation, and has been widely concerned. The semi-analytical nodal method (SANM) based on transverse-integrated neutron diffusion equation has the advantages of high accuracy and convenience for multi-group calculation. The 0th-order flux and the 2nd-order flux being Expanded with the existing 4th-order SANM polynomials and being solved respectively, the 4th-order algebraic accuracy flux distribution is also obtained, however, this solving process is not the semi-analytical nodal method since the polynomial expansion process does not take the special modality of SP3 equation and it’s analytical solution into consideration. There are two modality SP3 equation, so there are two SANM expansion forms. A code is developed to solve the SP3 equation under the two different forms. After the calculation of the same benchmark, the difference between the two forms of SP3 equation is found. According to the results, and in view of the special modality of the SP3 equation, advices for a strict semi-analytical method for solving SP3 equation are discussed.


Author(s):  
Changhui Wang ◽  
Hongchun Wu ◽  
Liangzhi Cao

A method of on-line monitoring the reactor core flux distribution is proposed in this paper. In this method, the real in-core flux distribution is reconstructed on-line using the eigenfunctions of neutron diffusion equation. we expand the real in-core flux distribution by the eigenfunctions with linear combination and calculate the expansion coefficients according to the fixed in-core detector readings which are the real-time response of in-core flux distribution. For only a few expansion coefficients need to be calculated in monitoring process, this method has a high calculation speed to meet the requirement of on-line monitoring the reactor. A program named NLSANM-K (Nonlinear Iteration Semi-Analytic Nodal Method & Krylov subspace method) is encoded to calculate the eigenfunctions. The accuracy of the reconstruction is verified by comparing the reconstructed flux distribution with the results calculated by a core simulator SAMME.


1990 ◽  
Vol 105 (3) ◽  
pp. 256-270 ◽  
Author(s):  
D. V. Altiparmakov ◽  
Dj. Tomašević

2013 ◽  
Vol 174 (2) ◽  
pp. 163-171 ◽  
Author(s):  
Yunzhao Li ◽  
Hongchun Wu ◽  
Liangzhi Cao

2018 ◽  
Vol 120 ◽  
pp. 869-879 ◽  
Author(s):  
Wen Yang ◽  
Hongchun Wu ◽  
Yunzhao Li ◽  
Liangzhi Cao ◽  
Sicheng Wang

Author(s):  
David V. Colameco ◽  
Kostadin N. Ivanov ◽  
Rian H. Prinsloo ◽  
Djordje I. Tomasevic ◽  
Suzanne Theron

The resurgence of high temperature reactor (HTR) technology has prompted the development and application of modern calculation methodologies, many of which are already utilized in the existing power reactor industry, to HTR designs. To this end, the use of nodal diffusion methods for full core neutronic analysis is once again considered for both their performance and accuracy advantages. Recently a number of different approaches to two-dimensional and 3D multigroup cylindrical nodal diffusion methods were proposed by various institutions for use in HTR and, specifically, pebble-bed modular reactor (PBMR) calculations. In this regard, we may mention the NEM code from the Pennsylvania State University based on the nodal expansion method and the OSCAR-4 code from NECSA, utilizing a conformal mapping approach to the analytic nodal method. In this work we will compare these two approaches in terms of accuracy and performance. Representative problems, selected to test the methods thoroughly, were devised and based on both a modified version of the PBMR 400 MW benchmark problem and a “cylindrisized” version of the IAEA two-group problem. The comparative results between OSCAR-4 and NEM are given, focusing on global reactivity estimation, as well as power and flux errors as compared with reference finite-difference solutions. These results indicate that both OSCAR-4 and NEM recover the global reference solution for the IAEA problem and show power errors, which are generally acceptable for nodal methods. For the PBMR problem the accuracy is similar, but some convergence difficulties are experienced at the outer boundaries of the system due to the very large dimensions of the reflector (when compared with typical water-moderated reactors). For both codes a significant performance increase was found, as compared with finite-difference calculations, which is the method currently employed by the PBMR (Pty) Ltd. In conclusion it seems that nodal methods have potential for use in the HTR analysis and, specifically, the PBMR calculational arena, although cylindrical geometry based nodal methods will have to develop toward maturity before becoming the industry standard.


Sign in / Sign up

Export Citation Format

Share Document