3. DESCRIPTION OF PROBLEM OR FUNCTION
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FORMAT: LASL transport theory programs
NUMBER OF GROUPS: 18-, 24-, and 25-group.
NUCLIDES: Al, B, Be, C, Cd, Cl, D, Ga, F-194, Fe, H, K, Li-6, Mo, Na, Ni, O, Pu-239, Pu-240, Pu-249, Th, U-233, U-235, U-238, and Zr.
ORIGIN: Los Alamos Scientific Laboratory _ Univ of California.
WEIGHTING SPECTRUM:
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Group constants and computed neutron cross sections are tabulated for a variety of materials including - Al, B, Be, C, Cd, Cl, D, Ga, F194, Fe, H, K, Li6, Mo, Na, Ni, O, Pu239, Pu240, Pu249, Th, U233, U235, U238, and Zr. These are presented as 18-, 24-, and 25-group calculations for reactors with neutron energies ranging from fast to thermal.