Radiation shielding information center data activities Page: 3 of 4
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technology among installations engaged in radiation
transport research, development, and application. A
partial listing of the current contents of the Data
Library Collection is given in Table 2.
The philosophy behind the packaging and distri-
buting of these data libraries is to preserve and
make available in a computer-readable form, data which
may be useful to those utilizing or performing radiation
transport calculations. Since this usually involves
the use of large computer programs, several of these
libraries are multigroup cross sections in the format
utilized by many such programs.
Documentation is very important. The abstract for-
mat used for the DLC7 sets is similar to that used to
describe the code packages. Care was taken to make
the format include all of the information necessary
for adequately describing the contents and purpose of
each data library. The main purpose of the abstracts
is to give to a potential data library user several
criteria for deciding whether or not he wishes to obtain
Present activities with sponsors (on behalf of their
contractors) has involved RSIC in projects where
processed cross section libraries are generated
directly for a particular user community. These activ-
ities on behalf of the DNA and CTR communities are
TABLE 2. Partial Contents of RSIC Data Library
Name Comments (Contributor)''
100 group, PB, neutron cross sections by
SUPERTOG from ENDF/B-III (ORNL).
Analyzed cascade calculation results for
n,p,- on several materials (ORNL).
Photon Interaction Library in ENDF format
Input data for benchmark problems in
Photon production library for POPOP4
Storm-Israel photon interaction library-
ENDF format (LASL).
DLC-16/ 123 group neutron cross sections from
COBB ENOF/B-II for XSDRN (ORNL).
DLC-18/ 100 group neutron cross sections used
NAB in analysis of ORNL-LMBF sodium
22-18 group coupled cross sections for
shipping cask analysis (ORNL).
100 group neutron reaction cross sections
for ENDF/B-III library (ORNL).
104-22 coupled cross sections by AMPX
for concrete elements (ORNL).
:2-21 coupled cross sections used in
ORNL CTR neutronics (ORNL).
DLC-29/ 100 group neutron kerma factors by MACK
FACKLIB from ENF/B-III (U. Wisc.)
TABLE 2 (continued)
DLC-30/ Radioactive decay data, EXREM III format,
DECAYRfE many materials (ORNL).
DLC-31/ Defense Nuclear Agency processed cross
DPL section library - multigroup data ANISN
format - point data SAM-CE format (ORNL,
DLC-33/ 100 group neutron activation cross sections
MONTAGE for CTR studies (LASL).
-Library contributors: ORNL, Oak Ridge National
Laboratcry, Oak Ridge, Tenn.; LLL, Lawrence Livermore
Laboratory, Livermore, Ca.; NBS, National Bureau of
Standards, Washington, D.C.; LASL, Los Alamos Scientific
Laboratory, Los Alamos, N.M.; U. Wisc., Nuclear Engin-
eering Department, U. Wisconsin, Madison, Wis.: MAGI,
Mathematical Applications Group, Inc., Elmsford, N.Y.
Special DNA Processed Cross Section Libraries
A new class of data libraries was developed
in cooperation with the DNA Radiation Transport Program.
They are identified as Data Library Collection 31
(DLC-31) and include both multigroup and point cross
section data. A coupled 37-neutron, 21-gamma-ray- 8
group library in ANISN format was generated at ORNL
from recent ENDF/B and DNA evaluations for many mater-
ials using the AMPX9 cross section processor. Doe-
imentation includes results of calculations of
neutron sources in air and concrete. Other sets of
data suitable for use in the SAM-CE10 Monte Carlo
code were generated at MAGI. They can be used to per-
form neutron, secondary gamma-ray, and primary gama-
ray transport calculations.
Special CTR Processed Cross Section Library
Using specifications developed through conver-
sations and correspondence with various members of the
CTR neutronics community, RSIC will direct the gener-
ation of a coupled 156-neutron and 23-gamma-ray multi-
group cross section set as the beginning of a CTR
Processed Data Library. Most of the materials were
taken from the ENDF/B-IV and DNA evaluated libraries.
Allowance is made for self-shielding and temperature
dependence using the Bondarenkoll scheme. The smooth
weighting function used has M:*arellian weighting for
the thermal group, a I/ slowing down spectrum tied to
a fission spectrum and joined at high energies to a
D-T broadened 14 MeV spectrum. The library will be
generated using a combination of the MINX12 neutron
processor and various modules of the AMPX code system
with output in the A-PX interface format. In the gen-
eration process, a new mocule for the AMPX system will
be programmed to perform tne interpolation and iter-
ation required to determine appropriate self-shielded
and temperature-broadened cross-section values for a
given problem. Special cross section handling codes
will be packaged with the data to permit the user to
allow for composition and temperature dependence for a
specific problem and/or to collapse the data to reduce
the group structure down to a number considered
reasonable for a specific calculation. It is antici-
pated that the library will also bs available in CCCC
Standards Activities in RSIC
A continuing project, in cooperation with the
American Nuclear Society, is to collect, edit, and
publish reference data in the form of "benchmark
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Roussin, R.W.; Maskewitz, B.F. & Trubey, D.K. Radiation shielding information center data activities, article, April 30, 1975; Oak Ridge, Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc1019241/m1/3/?rotate=90: accessed July 16, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.