Computer Code Name: NJOY91.119

Computer Code Number: P00171

Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.

Keywords:
covariance data processing
endf/b-v
endf format
gamma-ray cross section processing
gamma-ray production cross section processing
kerma
multigroup cross sections
neutron cross section processing
workstation

Computers:
CRAY
SUN
VAX
IBM RS/6000

Operating Systems:
UNIX

Languages:
FORTRAN 77

Publications:
INFORMAL DOCUMENTS (4/92, 5/92)
LA-12057-MS
LA-12740-M
LA-9303-M (ENDF-324)
LA-9303-M, VOL. I
LA-9303-M, VOL. II
LA-9303-M, VOL. III
LA-9303-M, VOL. IV
LA-UR 89-2057
LA-UR 89-2057 (6/89)
LANL MEMO T-2-L-10991
LANL MEMO T-2-L-10991 (6/87)
VOL. 1 (5/82), 2 (5/82),
VOL. 4 (12/85)

Distribution Media:
P00171 MFMWS -----1 TAPE CARTRIDGE TAR

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The Radiation Safety Information Computational Center (RSICC) collects, analyzes, maintains, and distributes software in the areas of radiation transport and safety. RSICC resides in the Nuclear Energy and Fuel Cycle Division (NEFCD) at Oak Ridge National Laboratory.