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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
V. Khromov, E. Kryuchkov, G. Tikhomirov, L. Goncharov, V. Kondakov
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 264-276
Technical Paper | doi.org/10.13182/NSE95-A28563
Articles are hosted by Taylor and Francis Online.
A new numerical method, the probabilistic method of discrete ordinates (PMDO) for solving multigroup transport equations in three-dimensional complex geometry, is presented. The method can be used for reactor core and shielding calculations. Integral equations are adopted for the angular flux in cells of arbitrary form. They are coupled by means of net currents defined at interfaces. The sphere of directions is arbitrarily subdivided into a number of angular diapasons. These diapasons, along with cell volume and pieces of cell surface, produce elementary phase domains, so the basic PMDO equations are the algebraic analogues of piece-wise coupled integral transport equations. They are written for neutron flux and currents integrated over corresponding phase domains. The coefficients of the equations discretely depend on the angular variable and have the meaning of probabilities of uncollided neutrons being transmitted between different phase domains. On the basis of algebraic equations separately obtained for coarse and fine domains, the global-local iterative PMDO scheme has also been developed specifically for calculations in extensive heterogeneous media. Together with the direct PMDO equations, the system of conjugate equations has been constructed for the calculation of neutron importance function related to various nonlinear functionals. Codes based on the method and some numerical applications, including examples related to criti-cality calculations and deep penetration problems, have been briefly discribed.