Package Details


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
The Radiation Safety Information Computational Center (RSICC) is a Department of Energy Specialized Information Analysis Center (SIAC) authorized to collect, analyze, maintain, and distribute computer software and data sets in the areas of radiation transport and safety. RSICC resides in the Reactor and Nuclear Systems Division (RNSD) at Oak Ridge National Laboratory.