Response matrix analysis for fast reactors
From national topical meeting on mathematical models and computational techniques for analysis of nuclear systems: Ann Arbor, Michigan, USA (8 Apr 1973). In mathematical models and computational techniques for analysis of nuclear systems. The highly heterogeneous core design typical of LMFBR's and the desire to predict both gross and local nuclear performance parameters accurately create a demand for reasonable cost neutronic calculational methods that will account for the geometric detail and neutron interactions in three dimensions. The response matrix approach that has been applied to thermal reactors has been extended and applied to LMFBR's using each hexagonal fuel assembly as a cell. Two-dimensional test case results for a bare core show good agreement of power distribution and reactivity with transport theory (S4,P/sub o/). 8 references. (auth)
- Research Organization:
- General Electric Co., Sunnyvale, CA; American Nuclear Society. Michigan Section
- NSA Number:
- NSA-29-006912
- OSTI ID:
- 4377315
- Report Number(s):
- CONF-730414-P2
- Resource Relation:
- Conference: National topical meeting on mathematical models and computational techniques for analysis of nuclear systems, Ann Arbor, Michigan, USA, 8 Apr 1973; Other Information: Orig. Receipt Date: 30-JUN-74; Related Information: Mathematical models and computational techniques for analysis of nuclear systems
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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Breeding
*FBR TYPE REACTORS
*LMFBR TYPE REACTORS- REACTOR KINETICS
CONFIGURATION
FUEL ASSEMBLIES
MATHEMATICAL MODELS
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
REACTIVITY
REACTOR LATTICE PARAMETERS
THREE-DIMENSIONAL CALCULATIONS
TWO-DIMENSIONAL CALCULATIONS LMFBR TYPE REACTORS