Direct-coupled-ray method for design-oriented 3-D transport analysis. [LMFBR]
A fast three-dimensional design oriented transport method has been developed for the solution of both neutron and gamma transport problems. It combines a nodal approach with analytic integral transport to achieve relative speed and accuracy. An analytic solution is obtained for the angular flux in each of the 14 directions defined by the six faces and eight corners of a cubic mesh block. The scheme used to accommodate high order anisotropic scattering is based on the formulation of ray-to-ray scattering probabilities in an integral sense. A variable mesh approximation has also been introduced to provide greater flexibility. The details of a DCR ..-->.. P/sub 1/ conversion technique have been developed but not yet implemented. The DCR method, as implemented in the TRANS3 code, has been used in a number of LMFBR shielding applications. These included a 1-D deep penetration configuration and one-, two-, and three-dimensional representations of the lower axial shield of the Clinch River Breeder Reactor (CRBR). Comparisons with ANISN and DOT-III solutions indicated good to excellent agreement in most situations.
- Research Organization:
- Oak Ridge National Lab., TN (USA); Carnegie-Mellon Univ., Pittsburgh, PA (USA)
- DOE Contract Number:
- W-7405-ENG-26; E(11-1)-2467
- OSTI ID:
- 7123292
- Report Number(s):
- CONF-770304-3; TRN: 77-007203
- Resource Relation:
- Conference: Analysis of nuclear systems, Tucson, AZ, USA, 28 Mar 1977; Other Information: Thesis. Submitted by J. A. Bucholz to Carnegie-Mellon Univ., Pittsburgh
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
LMFBR TYPE REACTORS
SHIELDING
NEUTRON DIFFUSION EQUATION
THREE-DIMENSIONAL CALCULATIONS
NEUTRON TRANSPORT
GAMMA RADIATION
PHOTON TRANSPORT
BREEDER REACTORS
ELECTROMAGNETIC RADIATION
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
IONIZING RADIATIONS
LIQUID METAL COOLED REACTORS
NEUTRAL-PARTICLE TRANSPORT
RADIATION TRANSPORT
RADIATIONS
REACTORS
210500* - Power Reactors
Breeding
654003 - Radiation & Shielding Physics- Neutron Interactions with Matter