Bounded flux-at-a-point estimators for multigroup Monte Carlo computer codes

Journal Article · Sun Apr 01 04:00:00 EST 1979 · Nucl. Sci. Eng.; (United States)

OSTI ID:6309761

Fraley, S K; Hoffman, T J

Two methods to improve the variance of statistical flux-at-a-point estimators over conventional unbounded estimators are developed that are readily implemented in multigroup Monte Carlo radiation transport computer codes. The theory behind the methods is developed, and the procedures for their application to Monte Carlo computer codes are outlined where necessary for clarity. Their application is demonstrated by the solution of a sample problem. These methods do not require a modification of the random walk, are easily implemented in multigroup Monte Carlo computer codes, and provide results that are comparable to other finite variance techniques.

• Research Organization: Oak Ridge National Lab., TN
• OSTI ID: 6309761
• Journal Information: Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 70:1; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CALCULATION METHODS
KINETICS
MONTE CARLO METHOD
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
RADIATION FLUX
REACTOR KINETICS
TRANSPORT THEORY