GAMTEC II - A Code for Generating Consistent Multigroup Constants Utilized in Diffusion and Transport Theory Calculations

Technical Report · Mon Mar 01 04:00:00 EST 1965

DOI:https://doi.org/10.2172/4586260· OSTI ID:4586260

Carter, L. L. ^[1]; Richey, C. R. ^[1]; Hughey, C. E. ^[1]

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1. Battelle Pacific Northwest Labs., Richland, WA (United States)

The GAMTEC II code generates multigroup constants in the energy range from 0 to 10 MeV for either homogeneous mixtures or heterogeneous arrays of cylindrical fuel elements. The thermal group constants are average over either (1) Wigner-Wilkins light moderator spectrum, (2) Wilkins heavy moderator spectrum, or (3) Maxwellian distribution. For heterogeneous arrays, the spacial thermal flux is calculated by the P₃ approximation. For epithermal energies, the slowing down distribution is described by either a P₁ or B₁ approximation to the Boltzman equation. Resonance absorption is calculated by the Adler-Nordheim method. Fast fission corrections are calculated by an n-flight collision probability technique. Multigroup constants are punched on cards in both HFN (diffusion theory) and DTF (S_n transport theory) formats.

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(45-1)-1830
• NSA Number: NSA-19-037759
• OSTI ID: 4586260
• Report Number(s): BNWL-35
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
ABSORPTION
Adler-Nordheim Method
BOLTZMANN EQUATION
Boltzman Equation
COMPUTERS
CYLINDERS
Criticality
DIFFERENTIAL EQUATIONS
DIFFUSION
DISTRIBUTION
ENERGY
ENERGY RANGE
EPITHERMAL NEUTRONS
EV RANGE
FAST NEUTRONS
FISSION
FUEL ELEMENTS
GAMTEC II
GROUP THEORY
HOMOGENEOUS REACTORS
Heavy Moderator Spectrum
KEV RANGE
LEGENDRE FUNCTIONS
Light Moderator Spectrum
MATHEMATICS
MEV RANGE
MODERATORS
NEUTRON FLUX
NEUTRONS
NUMERICALS
Nuclear Criticality Safety Program (NCSP)
PROBABILITY
PROGRAMMING
RESONANCE ESCAPE PROBABILITY
RESONANCE NEUTRONS
SPECTRA
STATISTICS
Safety
THERMAL NEUTRONS
TRANSPORT THEORY