Monte Carlo shielding analyses using an automated biasing procedure

Journal Article · Mon Aug 01 04:00:00 EDT 1988 · Nucl. Sci. Eng.; (United States)

OSTI ID:6529574

Tang, J S; Hoffman, T J ^[1]

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1. Oak Ridge National Lab., Computing and Telecommunications Div., P.O. Box X, Oak Ridge, TN (US)

A systematic and automated approach for biasing Monte Carlo shielding calculations is described. In particular, adjoint fluxes from a one-dimensional discrete ordinates calculation are used to generate biasing parameters for a Monte Carlo calculation. The entire procedure of adjoint calculation, biasing parameters generation, and Monte Carlo calculation has been automated. The automated biasing procedure has been applied to several realistic deep-penetration shipping cask problems. The results obtained for neutron and gamma-ray transport indicate that with the automated biasing procedure Monte Carlo shielding calculations of spent-fuel casks can be easily performed with minimum effort and that accurate results can be obtained at reasonable computing cost.

• OSTI ID: 6529574
• Journal Information: Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 99:4; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420204 -- Engineering-- Shipping Containers
654001* -- Radiation & Shielding Physics-- Radiation Physics
Shielding Calculations & Experiments
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
AUTOMATION
CALCULATION METHODS
CASKS
CONTAINERS
DISCRETE ORDINATE METHOD
ELECTROMAGNETIC RADIATION
GAMMA RADIATION
GAMMA TRANSPORT THEORY
IONIZING RADIATIONS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
RADIATION TRANSPORT
RADIATIONS
SHIELDING
SPENT FUEL CASKS
TRANSPORT THEORY