TORT; A three-dimensional discrete ordinates neutron/photon transport code

Journal Article · Mon Apr 01 00:00:00 EST 1991 · Nuclear Science and Engineering; (United States)

OSTI ID:5251029

Rhoades, W A; Childs, R L ^[1]

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1. Oak Ridge National Lab., TN (United States)

This paper reports on TORT which calculates the flux or fluence of particles throughout a two- or three-dimensional geometric system from particles incident on the system from extraneous sources or generated internally as a result of interaction with the system. The principal application is for the deep-penetration transport of neutrons and photons. Certain reactor eigenvalue problems can also be solved. Numerous printed edits of the results are available, and many results can be transferred to output files for subsequent analysis.

• OSTI ID: 5251029
• Journal Information: Nuclear Science and Engineering; (United States), Vol. 107:4; ISSN 0029-5639
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
DISCRETE ORDINATE METHOD
NEUTRON TRANSPORT
CALCULATION METHODS
PHOTON TRANSPORT
POWER REACTORS
NEUTRON FLUX
EIGENVALUES
REACTOR KINETICS
T CODES
THREE-DIMENSIONAL CALCULATIONS
COMPUTER CODES
KINETICS
NEUTRAL-PARTICLE TRANSPORT
RADIATION FLUX
RADIATION TRANSPORT
REACTORS
220100* - Nuclear Reactor Technology- Theory & Calculation