GAFGAR; p3t; PROC; TAPCOP; spectra and group-averaged cross section calculation. [UNIVAC1108; FORTRAN IV]
Technical Report
·
OSTI ID:6489001
The problem is to obtain very detailed neutron flux and current distributions as functions of energy considering explicitly the possible overlap effects between resonances of a resonance absorber and of mixtures of resonance absorbers and to use these distributions to prepare group-averaged cross sections and transfer arrays for use in fast reactor analyses.UNIVAC1108; FORTRAN IV; EXEC2, GAX33A; 52K of available fast memory and 5 magnetic tape units plus 5 scratch files (drum files are used on the UNIVAC1108) totaling about 600K in capacity.
- Research Organization:
- General Atomic Co., San Diego, CA (USA)
- OSTI ID:
- 6489001
- Report Number(s):
- ANL/NESC-316; ON: DE83048316
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
ABSORPTION
COMPUTER CODES
CROSS SECTIONS
EPITHERMAL REACTORS
FAST REACTORS
G CODES
MULTIGROUP THEORY
NEUTRON FLUX
NEUTRON SPECTRA
NEUTRON TRANSPORT THEORY
RADIATION FLUX
REACTORS
RESONANCE ABSORPTION
SPECTRA
TRANSPORT THEORY
220100* -- Nuclear Reactor Technology-- Theory & Calculation
ABSORPTION
COMPUTER CODES
CROSS SECTIONS
EPITHERMAL REACTORS
FAST REACTORS
G CODES
MULTIGROUP THEORY
NEUTRON FLUX
NEUTRON SPECTRA
NEUTRON TRANSPORT THEORY
RADIATION FLUX
REACTORS
RESONANCE ABSORPTION
SPECTRA
TRANSPORT THEORY