1. NAME AND TITLE OF DATA LIBRARY
MENSLIB: 60 Group, P5, Cross Sections in DTF-IV for Transport Calculations for Neutrons
with Energies Up to 60 MeV.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
No retrieval program is included in the package.
Los Alamos Scientific Laboratory, Los Alamos, New Mexico.
4. HISTORICAL BACKGROUND AND INFORMATION
MENSLIB is a 60-group, P5 transport cross section library for H, B, C, N, O, Si, Fe, and W. It was developed for use in the analysis and design of a shield-collimator unit for use in medium-energy neutron cancer therapy.
Although the library is applicable to a variety of particle accelerator neutron shielding problems,
it was specifically developed for shielding calculations in gray cast iron and water-extended-polyester
(WEP) with the spectrum of neutrons produced by 50 MeV deuterons on Be.
5. APPLICATION OF THE DATA
The library is applicable to medium-energy neutron multigroup transport calculations.
6. SOURCE AND SCOPE OF DATA
The library combines ENDF/B-IV data processed by the NJOY code, medium energy data calculated with the intranuclear cascade + evaporation code CROIX, and medium-energy nonelastic cross-section magnitudes estimated from experimental data where available. Elastic scattering above 20 MeV is ignored for all nuclides other than hydrogen. Infinitely dilute cross sections are provided for each of the eight materials of the library.
The 60 group nuclear data library created for medium energy neutron transport calculations to be
used in nuclear data development and shield design for neutrons below 60 MeV is as follows:
H, B, C, N, O, Si, Fe, W.
Note: Multiply by (2L+1) before using in ANISN.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAMS
8. DATA FORMAT AND COMPUTER
BCD to Binary conversion; IBM 370.
9. TYPICAL RUNNING TIME
W. B. Wilson, "Nuclear Data Development and Shield Design for Neutrons Below 60 MeV,"
LASL report LA-7159-T (February 1978).
11. CONTENTS OF LIBRARY
Included are the referenced documents and one (1.2MB) DOS diskette which contains the data
library and the source for BCD to binary conversion and the IBM JCL to run the conversion, plus
output from the BCD to binary conversion.
12. DATE OF ABSTRACT
KEYWORDS: INTRANUCLEAR CASCADE; MULTIGROUP CROSS SECTIONS; MULTIGROUP CROSS SECTIONS BASED ON ENDF/B; NEUTRON CROSS SECTIONS