Error analysis of the quartic nodal expansion method for slab geometry
Conference
·
OSTI ID:10122628
- North Carolina State Univ., Raleigh, NC (United States)
- Oak Ridge National Lab., TN (United States)
This paper presents an analysis of the quartic polynomial Nodal Expansion Method (NEM) for one-dimensional neutron diffusion calculations. As part of an ongoing effort to develop an adaptive mesh refinement strategy for use in state-of-the-art nodal kinetics codes, we derive a priori error bounds on the computed solution for uniform meshes and validate them using a simple test problem. Predicted error bounds are found to be greater than computed maximum absolute errors by no more than a factor of six allowing mesh size selection to reflect desired accuracy. We also quantify the rapid convergence in the NEM computed solution as a function of mesh size.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10122628
- Report Number(s):
- CONF-950420-19; ON: DE95007373; TRN: 95:002593
- Resource Relation:
- Conference: International conference on mathematics and computations, reactor physics, and environmental analyses,Portland, OR (United States),30 Apr - 4 May 1995; Other Information: PBD: [1995]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
NUMERICAL SOLUTION
ACCURACY
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NEUTRON TRANSPORT
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N CODES
663610
220100
990200
NEUTRON PHYSICS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
NUMERICAL SOLUTION
ACCURACY
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT
COMPUTERIZED SIMULATION
N CODES
663610
220100
990200
NEUTRON PHYSICS
THEORY AND CALCULATION
MATHEMATICS AND COMPUTERS