FUEL ELEMENTS NUCLEAR DESIGN PROGRAM
Technical Report
·
OSTI ID:4795301
ABS>ANP 704 digital program No. 381, which was used to perform the bulk of the nuclear calculations for the D103A fuel element design is described. This program handles the iterative fine power fiattening of concentric ring fuel elements of the D103A type. Input consists of gross element geometry, basic nuclear data and various mechanical parameters. Output consists of the fine geometry of the element, the fine power profile, and partially processed thermodynamic data. The thermodynamic data are also punched in a form suitable for use as input to ANP program No. 23, Flow Through Heated Annuli. (auth)
- Research Organization:
- General Electric Co. Aircraft Nuclear Propulsion Dept., Cincinnati
- DOE Contract Number:
- AT(11-1)-171; AF33(038)-21102; AND AF33(600)-38062
- NSA Number:
- NSA-16-014320
- OSTI ID:
- 4795301
- Report Number(s):
- XDC-59-11-94
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-62
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
REACTOR TECHNOLOGY
AIRCRAFT
BUCKLING
COMPUTERS
CONFIGURATION
CROSS SECTIONS
DENSITY
DIGITAL SYSTEMS
DISTRIBUTION
ENERGY
ENERGY RANGE
EPITHERMAL NEUTRONS
EQUATIONS
FAST NEUTRONS
FUEL ELEMENTS
HEAT TRANSFER
MATERIALS TESTING
MATHEMATICS
MECHANICAL STRUCTURES
MULTIPLICATION FACTORS
NEUTRON FLUX
NUMERICALS
PLANNING
POWER PLANTS
PROGRAMMING
PROPULSION
REACTOR CORE
RESONANCE ESCAPE PROBABILITY
RESONANCE NEUTRONS
STANDARDS
TEMPERATURE
THERMAL CONDUCTIVITY
THERMAL NEUTRONS
THERMAL UTILIZATION
THERMODYNAMICS
TRANSPORT THEORY
VARIATIONS
ZONES
AIRCRAFT
BUCKLING
COMPUTERS
CONFIGURATION
CROSS SECTIONS
DENSITY
DIGITAL SYSTEMS
DISTRIBUTION
ENERGY
ENERGY RANGE
EPITHERMAL NEUTRONS
EQUATIONS
FAST NEUTRONS
FUEL ELEMENTS
HEAT TRANSFER
MATERIALS TESTING
MATHEMATICS
MECHANICAL STRUCTURES
MULTIPLICATION FACTORS
NEUTRON FLUX
NUMERICALS
PLANNING
POWER PLANTS
PROGRAMMING
PROPULSION
REACTOR CORE
RESONANCE ESCAPE PROBABILITY
RESONANCE NEUTRONS
STANDARDS
TEMPERATURE
THERMAL CONDUCTIVITY
THERMAL NEUTRONS
THERMAL UTILIZATION
THERMODYNAMICS
TRANSPORT THEORY
VARIATIONS
ZONES