Control Rod Programming Part II: Two-Group Theory of General Configuration
- Alco Products, Inc., Schenectady, NY (United States)
In Part 1 of the present series of reports, an investigation of the possibilities of buckling calculations for partly inserted control rods was made on the one-group neutron diffusion model. The results were highly indicative that extension to the two-group model was possible. The study is continued in this report, in which is given a method for determining buckling (and hence reactivity) of a general array of partly inserted control rods in a cylindrical bare equivalent reactor. At this stage of development of the theory, fuel burnup is not yet specifically included; criticality is provided implicitly by variation of the effective number of neutrons per fission. The buckling is found to be calculable from suitable flux averages over the various regions of the operating core.
- Research Organization:
- Alco Products, Inc., Schenectady, NY (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- NSA Number:
- NSA-19-031496
- OSTI ID:
- 4594464
- Report Number(s):
- AP-Note-399
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BUCKLING
BURNUP
Buckling
Burnup
CONFIGURATION
CONTROL ELEMENTS
CONTROL SYSTEMS
CRITICALITY
CYLINDERS
Configuration
Control Elements
Control Systems
Criticality
Criticality Studies
Cylinders
DELAYED NEUTRONS
DIFFUSION
DISTRIBUTION
Delayed Neutrons
Diffusion
Distribution
ENERGY
Energy
FISSION
FUELS
Fission
Fuels
NEUTRON FLUX
NEUTRONS
NUMERICALS
Neutron Flux
Neutrons
Nuclear Criticality Safety Program (NCSP)
Numericals
OPERATION
Operation
PROMPT NEUTRONS
Prompt Neutrons
REACTIVITY
REACTOR CORE
REACTORS
RODS
Reactivity
Reactor Core
Reactor Technology
Reactors
Rods
VARIATIONS
Variations
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BUCKLING
BURNUP
Buckling
Burnup
CONFIGURATION
CONTROL ELEMENTS
CONTROL SYSTEMS
CRITICALITY
CYLINDERS
Configuration
Control Elements
Control Systems
Criticality
Criticality Studies
Cylinders
DELAYED NEUTRONS
DIFFUSION
DISTRIBUTION
Delayed Neutrons
Diffusion
Distribution
ENERGY
Energy
FISSION
FUELS
Fission
Fuels
NEUTRON FLUX
NEUTRONS
NUMERICALS
Neutron Flux
Neutrons
Nuclear Criticality Safety Program (NCSP)
Numericals
OPERATION
Operation
PROMPT NEUTRONS
Prompt Neutrons
REACTIVITY
REACTOR CORE
REACTORS
RODS
Reactivity
Reactor Core
Reactor Technology
Reactors
Rods
VARIATIONS
Variations