Neutron and gamma transport effects by heterogeneous core designs. [LMFBR]
Conference
·
OSTI ID:5100330
The use of diffusion theory for the prediction of power production near a reactor core-blanket interface and the assumption that gammas are absorbed in situ can lead to substantial errors. This is primarily due to the breakdown of Fick's law for neutron diffusion near the core-blanket boundary, and the gamma leakage from the core into the blanket. These considerations are more pronounced in a situation where a large number of internal blanket assemblies are present, such as in the large heterogeneous core designs. The power distribution is studied for both fission and gamma heating in a large heterogeneous LMFBR with 3 core zones separated by 2 internal blanket zones. Comparisons are made between diffusion and transport theory for neutronics calculations, and between in-situ absorption and rigorous transport theory calculation for gamma heating.
- Research Organization:
- Argonne National Lab., Ill. (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5100330
- Report Number(s):
- CONF-770611-34
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEATING
HETEROGENEOUS EFFECTS
KINETICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
POWER DENSITY
RADIATION HEATING
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
TRANSPORT THEORY
210500* -- Power Reactors
Breeding
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEATING
HETEROGENEOUS EFFECTS
KINETICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
POWER DENSITY
RADIATION HEATING
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
TRANSPORT THEORY