ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Apr 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
June 2026
Nuclear Technology
March 2026
Fusion Science and Technology
May 2026
Latest News
DOE selects first companies for nuclear launch pad
The Department of Energy’s Office of Nuclear Energy and the National Reactor Innovation Center have announced their first selections for the Nuclear Energy Launch Pad: three companies developing microreactors and one developing fuel supply.
The four companies—Deployable Energy, General Matter, NuCube Energy, and Radiant Industries—were selected from the initial pool of Reactor Pilot Program and Fuel Line Pilot Program applicants, the two precursor programs to the launch pad.
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.