1. NAME AND TITLE OF DATA LIBRARY
DOSDAM77-81: 620 Group, SAND-II Formatted, Neutron Cross Sections based on
ENDF/B-IV and Other Sources for Spectral, Integral, and Damage
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
Program for listing the DOSDAM77-81 library data.
Netherlands Energy Research Foundation, Petten (N.H.), Netherlands.
4. HISTORICAL BACKGROUND AND INFORMATION
The library is a compilation of evaluated cross section data sets for activation neutron spectrometry and for interpretation of neutron spectrometry results in terms of displacements per atom and in characteristic neutron spectrum values. The SAND-II fine groups structure with 620 groups is used in this compilation.
The sources of evaluated neutron cross section sets were: 1) ENDF/B-IV dosimetry file; 2) SAND-II (DETAN74) of BNL; 3) LAPENAS from Dr. A. A. Lapenas of Riga; 4) CESNEF nuclear data
group of CNEN (Bologna); 5) titanium cross section data from Dr. C. Philis et al. from ANL; 6)
EWGRD recommendations (report EUR 5274); 7) vanadium and niobium damage cross section sets
from Dr. Alberan from CEN Saclay; 8) old ECN damage cross section set library.
5. APPLICATION OF THE DATA
The fine group cross section data of this library are suited especially for neutron spectrometry by means of activation detectors.
The library contains the cross section sets for a number of well-known activation detectors. The format of the library originates from the SAND-II program packet. For this reason, the library can be used directly for the unfolding programs SAND-II and CRYSTAL BALL. The application of this library for other unfolding programs can, in general, be obtained with small utility programs.
The neutron spectrum obtained from the unfolding procedure can be used to calculate the number of displacements per atom and, if required, other data characterizing the neutron spectrum (i.e., total flux density, flux density above 1 MeV, average neutron spectrum energy, etc.).
For the calculation of values characterizing the neutron spectrum, artificial cross section sets are
incorporated in the library (see report ECN-36). The calculation of the DPA and characteristic
spectrum values can be accomplished with the program SAND-II or with a special utility program.
6. SOURCE AND SCOPE OF DATA
The original data were either available in the 620 groups SAND-II format or they were converted to this format with programs like CSTAPE of the CCC-112/SAND-II program package. Included in the package is the DOSCROSS77 dosimetry cross section library which is based on the ENDF/B-IV dosimetry file, supplemented with some other evaluations. The total number of reaction cross section sets in DOSCROSS77 is 49 (+3 cover cross section sets). Also included in the package is DAMSIG77, damage cross sections of the following materials: graphite, stainless steel, aluminum, silicium, chromium, iron, nickel, copper, zirconium, molybdenum, tungsten, vanadium, and niobium. A number of these materials have more than one cross section set, originating from different evaluations.
Cross sections for some activation reactions, commonly used to determine thermal and fast neutron fluences have been included as well as some artificial cross sections which can be used to derive values for some physical quantities which may characterize neutron spectra.
Data for 49 reactions with the following elements are given:
Li, B, Na, Al, P, S, Sc, Ti, Fe, Mn, Ni, Co, Cu, Zn, Zr, Ag, Rh, In, I, Ta, Au, Au, Th, U, Np, Pu,
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
The retrieval program should be suitable to read cross section data sets in the SAND-II format.
The energy values forming the 620 groups' structure are listed in BNWL-1312. The cross section data
in the library are expressed in units of barn (1028m2).
8. DATA FORMAT AND COMPUTER
EBCDIC card images; CDC 6400.
9. TYPICAL RUNNING TIME
W. L. Zijp, H. J. Nolthenius, and N. J. C. M. van der Borg, "Cross Section Library DOSCROSS77 (in the SAND-II format)," EGN-25 (August 1977).
W. L. Zijp, K. H. Appelman, H. J. Nolthenius, and H. CH. Rieffe, "Damage Cross Section
Library (DAMSIG77)," ECN-36 (February 1978).
11. CONTENTS OF LIBRARY
Included are the referenced documents and one (1.2MB) DOS diskette which contains activation
and damage reaction rate cross sections in SAND-II 620 group format and a retrieval program for
listing the DOSDAM77-81 library.
12. DATE OF ABSTRACT
June 1981; revised May 1985.
KEYWORDS: NEUTRON CROSS SECTIONS