KARE--A SYSTEM OF DIFFUSION THEORY PROGRAMS FOR THE PHILCO 2000. VOLUME I. GENERAL DESCRIPTION, INPUT INSTRUCTIONS, AND OUTPUT DETAILS

Technical Report · Tue Nov 20 04:00:00 EST 1962

OSTI ID:4713448

Archibald, Jr, J A; Teaford, H L

The present KARE system provides semiautomatic calculations of neutron group constants, criticality, spatial distribution of neutron fluxes and fission sources, fuel and poison depletion, and lumped fission fragment poisoning effects throughout life. The group constant calculations are done by solving the few- group approximations of the multigroup diffusions which may be cylindrical, rectangular, or hexagonal (also referred to as triangular). In the two latter cases, diagonal mesh boundaries and region interfaces are permitted. KARE also includes a multichannel flux synthesis calculation, perturbation calculations, a calculation of gamma radiations, and a calculation of space- and spectrum- dependent thermal fluxes. A general technical description of the entire system and a detailed description of the input and output are given. (auth)

• Research Organization: Knolls Atomic Power Lab., Schenectady, N.Y.
• DOE Contract Number: W-31-109-ENG-52
• NSA Number: NSA-17-022532
• OSTI ID: 4713448
• Report Number(s): KAPL-2165-1
• Country of Publication: United States
• Language: English

Related Subjects

BURNUP
COMPUTERS
CRITICALITY
DIFFUSION
DISTRIBUTION
FISSION
FISSION PRODUCTS
GAMMA RADIATION
KARE-CODE
NEUTRON FLUX
NEUTRONS
NUMERICALS
PERTURBATION THEORY
PHILCO 2000
PHYSICS
POISONING
PROGRAMMING
QUANTITY RATIO