Solution to the multigroup neutron transport equations in an infinite medium

Conference · Thu Jan 01 04:00:00 EST 1987 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5511118

Ganapol, B D; Baker, R S

An accurate numerical evaluation of the multigroup neutron flux in an infinite medium has long been a goal sought after by numerical transport analysts, since it is this problem that brings analytical solutions from the purely academic to the practical. This paper is addressed in part to the criticism of the analytical benchmarking effort, and in part to code developers and educators, for the authors present a reliable numerical solution to the multigroup neutron transport equations in an infinite medium as an alternative to the F/sub N/ method. This solution has practical application both in assessing numerical transport algorithms and in generating collapsed multigroup data. The solution techniques employs nothing more than a Fourier transformation whose origins date back to Case, de Hoffman, and Placek's now-famous investigation.

• Research Organization: Univ. of Arizona, Tucson
• OSTI ID: 5511118
• Report Number(s): CONF-870601-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 54
• Country of Publication: United States
• Language: English

Related Subjects

654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ACCURACY
ALGORITHMS
BENCHMARKS
FOURIER TRANSFORMATION
GROUP THEORY
INTEGRAL TRANSFORMATIONS
MATHEMATICAL LOGIC
MATHEMATICS
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
RADIATION FLUX
SLOWING-DOWN
TRANSFORMATIONS
TRANSPORT THEORY