APPLICATION OF PYTHON PROGRAMMING TOOLS FOR CRITICALITY SIMULATION OF NEUTRON TRANSPORT IN NUCLEAR REACTOR WITH SLAB GEOMETRY

Ngày nhận bài: 22-07-2015

Ngày duyệt đăng: 03-09-2015

DOI:

Lượt xem

0

Download

0

Chuyên mục:

KỸ THUẬT VÀ CÔNG NGHỆ

Cách trích dẫn:

Quan, L., & Thanh, N. (2024). APPLICATION OF PYTHON PROGRAMMING TOOLS FOR CRITICALITY SIMULATION OF NEUTRON TRANSPORT IN NUCLEAR REACTOR WITH SLAB GEOMETRY. Tạp Chí Khoa học Nông nghiệp Việt Nam, 13(6), 1016–1027. http://testtapchi.vnua.edu.vn/index.php/vjasvn/article/view/1535

APPLICATION OF PYTHON PROGRAMMING TOOLS FOR CRITICALITY SIMULATION OF NEUTRON TRANSPORT IN NUCLEAR REACTOR WITH SLAB GEOMETRY

Luong Minh Quan (*) 1 , Nguyen Thi Thanh 1

  • 1 Faculty of Information Technology, Viet Nam National University of Agriculture
  • Tóm tắt


    Monte Carlo criticality calculations use the power iteration method to determine the eigenvalue () and eigenfunction (fission source distribution) of the fundamental mode. However, the main problems of this method are the slow convergence of fission source distribution from the initial guess to the stationary solution, and the correlation between successive cycles which results in an under-prediction bias in the confident intervals of the estimated response. In this paper, we presented the Wielandt's method aiming to accelerate the convergence of the Monte Carlo power iteration.The object-oriented programming called Python prototype, was used to describe the standard Monte Carlo criticality power iterations for mono-kinetic particles and to compare the results obtained by the two different methods of acceleration mentioned above. The Wielandt's method successfully suppressed the auto-correlation, even though no gain in the figure of merit seemed to occur.

    Tài liệu tham khảo

    Brian, C. Kiedrowski, Forrest B (2008). Brown. Using Wielandt’s Method to Eliminate Confidence Interval Underprediction Bias in MCNP5 Criticality Calculations.

    Brown F. (2005). Fundamentals of Monte Carlo Particle Transport. LAUR -05-4983, Los Alamos National Laboratory.

    Fausto Malvagi, Eric Dumonteil, Francois-Xavier Hugot (2012). Les bonnes pratiques dans les calculs critiques en Monte Carlo. Commissariat a l’Energie Atomique DEN/DANS/DM2S/SERMA.

    https://docs.python.org/2/tutorial/

    https://root.cern.ch/drupal/

    Kitada T., T. Takeda (2000). Effective Convergence of Fission Source Distribution in Monte Carlo Simulation. J. Nucl. Sci. Techlo., 38(5): 324 - 329.

    Paul Reuss (2008). Neutron Physics. Institute National des Sciences et Techniques Nuclear.