Discrete nodal integral transport-theory method for multidimensional reactor physics and shielding calculations
Conference
·
OSTI ID:6337991
A coarse-mesh discrete nodal integral transport theory method has been developed for the efficient numerical solution of multidimensional transport problems of interest in reactor physics and shielding applications. The method, which is the discrete transport theory analogue and logical extension of the nodal Green's function method previously developed for multidimensional neutron diffusion problems, utilizes the same transverse integration procedure to reduce the multidimensional equations to coupled one-dimensional equations. This is followed by the conversion of the differential equations to local, one-dimensional, in-node integral equations by integrating back along neutron flight paths. One-dimensional and two-dimensional transport theory test problems have been systematically studied to verify the superior computational efficiency of the new method.
- Research Organization:
- Argonne National Lab., IL (USA); Illinois Univ., Urbana (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6337991
- Report Number(s):
- CONF-800942-22; ON: DE81023880
- Country of Publication:
- United States
- Language:
- English
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