SYN; 2-dimensional synthesis multigroup diffusion and 1-group depletion. [GE635; FORTRAN IV and GMAP]

Technical Report ·

OSTI ID:6489486

Kelley, M D

SYN contains two major segments, BISYN and BICYCL. The BISYN segment solves the two-dimensional multigroup neutron diffusion theory equations in r,z or x,y geometry using a noniterative synthesis method. This approach is designed to greatly reduce the computer cost of running two-dimensional multigroup problems at the risk of some loss in accuracy of the detailed flux distribution. This segment also contains a perturbation and effective delayed neutron fraction calculation. The BICYCL segment uses output from BISYN to solve the one-group neutron depletion equations. BICYCL allows the user to search on makeup or recycle isotopic compositions for a first cycle of a first core or for equilibrium concentrations. It also has provisions for fuel shuffling and the option to cycle back to BISYN in order to update the fluxes, one-group cross sections, etc.GE635; FORTRAN IV and GMAP; GECOS III; 51K of fast memory, 2 tape drives and 821,760 words of peripheral storage.

• Research Organization: General Electric Co., Sunnyvale, CA (USA). Breeder Reactor Development Operation
• OSTI ID: 6489486
• Report Number(s): ANL/NESC-495; ON: DE83048495
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
COMPUTER CODES
DIFFERENTIAL EQUATIONS
EQUATIONS
F CODES
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
PERTURBATION THEORY
R CODES
RADIATION FLUX
T CODES
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS