CALCULATION OF THERMAL NEUTRON DIFFUSION LENGTH AND GROUP CROSS SECTIONS: THE GLEN PROGRAM.
- Research Organization:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-7405-ENG-36
- NSA Number:
- NSA-22-032432
- OSTI ID:
- 4507060
- Report Number(s):
- LA-3893
- Resource Relation:
- Other Information: UNCL. Orig. Receipt Date: 31-DEC-68
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
N36100* -Physics (Nuclear)-Neutron Interactions with Matter
CDC 6600
COMPUTERS
CROSS SECTIONS
DIFFERENTIAL EQUATIONS
DIFFUSION LENGTH
FORTRAN
GLEN-CODE
LEGENDRE FUNCTIONS
NEUTRON BEAMS
NEUTRON FLUX
PROGRAMMING
SPECTRA
THERMAL NEUTRONS
NEUTRONS
THERMAL/diffusion lengths for
computer program for calculating
(T)
NEUTRON CROSS SECTIONS/calculation of group thermal
computer program for
(T)
COMPUTER PROGRAMS/GLEN
for calculating thermal neutron diffusion lengths and group cross sections
FORTRAN IV for CDC 6600
CDC 6600
COMPUTERS
CROSS SECTIONS
DIFFERENTIAL EQUATIONS
DIFFUSION LENGTH
FORTRAN
GLEN-CODE
LEGENDRE FUNCTIONS
NEUTRON BEAMS
NEUTRON FLUX
PROGRAMMING
SPECTRA
THERMAL NEUTRONS
NEUTRONS
THERMAL/diffusion lengths for
computer program for calculating
(T)
NEUTRON CROSS SECTIONS/calculation of group thermal
computer program for
(T)
COMPUTER PROGRAMS/GLEN
for calculating thermal neutron diffusion lengths and group cross sections
FORTRAN IV for CDC 6600