CRYO-S(A,B)-ACE1 - Scattering Law and Continuous Energy Cross Section Library of Materials at Cryogenic Temperatures.
NJOY99, MCNP5, MCNPX
Universitaet Stuttgart, Institut fuer Kernenergetik und Energiesysteme, Stuttgart, Germany through the Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France.
Efforts devoted to developing or improving thermal
scattering data (S(alpha,beta)) for very cold and cryogenic temperatures have
recently been carried out. Here several evaluations carried out at the Institut
fur Kernenergetik und Energiesysteme (IKE), University of Stuttgart are made
available.
5. APPLICATION OF THE DATA
The datasets are provided in the standard ENDF-6 format and in the ACE format, used for continuous energy Monte Carlo applications. Cross section libraries can be produced also for deterministic approaches through the use of the NJOY computer code. It should be noted that for very cold temperatures special care must be taken in processing the data and occasionally patches need to be applied to the processing code.
Processing of the S(alpha,beta) data to energy dependent differential and integral cross sections as well as data sets for neutron transport calculations has been carried out e.g. MCNP(X). This was done with the following sequence of modules from NJOY-99.161: RECONR - BROADR - THERMR - ACER. ACE format files were generated for use with the Monte Carlo codes MCNP-4, MCNP-5 and MCNPX-2.6. These processed data were used for validation of calculated neutron cross sections with experimental data of which part is presented in the report.
Liquid hydrogen and deuterium for the two modifications:
ortho and para
Material MAT* Temperatures
(K) ID ACE* files
para Hydrogen 2 14,
16 and 20.38 pH.00t, pH.01t, pH.03t
ortho Hydrogen 3 14, 16 and
20.38 oH.00t, oH.01t, oH.03t
para Deuterium 12 19 and
23.65 pD.00t, pD.01t
ortho Deuterium 13 19 and
23.65 oD.00t, oD.01t
H in polyethylene (CH2)
Material MAT Temperatures
(K) ID ACE files
H in
CH2 37 87,
293.6 and 350 poly.01t, poly.03t, poly.04t
poly.11t,
poly.13t, poly.14t
Liquid argon
Material MAT Temperature
(K) ID ACE file
18-Ar 18 87 argon.01t,
argon.11t
Aluminium face centred cubic lattice
Material MAT Temperatures
(K) ID ACE
files
13-Al-27 61 20, 77, 87, 100,
293.6, 400 al.00t,al.01t,al.02t,al.03t,
al.04t,al.05t,
al.10t,al.11t,al.12t,al.13t,
al.14t,al.15t
* MAT numbers for the ENDF files and ID's for ACE (MCNP continuous energy data
libraries)
Processing of the S(alpha,beta) data to energy dependent differential and integral cross sections as well as data sets for neutron transport calculations has been carried out e.g. MCNP(X). This was done with the following sequence of modules from NJOY-99.161: RECONR - BROADR - THERMR - ACER.
UNIX workstation, PC, or Mac (D00253MNYCP00).
N/A
a. Documentation included with library
M. Mattes and J. Keinert, “Present Status of Evaluated Thermal Neutron Scattering Data in the Temperature Range 20 K < T < 300 K for Solid and Liquid Moderator Materials Important for Design of Cold Neutron Sources,” IKE - University of Stuttgart, JEFF Meeting November 2005.
M. Mattes, “MAT Numbers for the ENDF Files and ID's for the ACE Thermal Files,” IKE, Universitaet Stuttgart, Germany.
M. Mattes, “Validation of the Thermal Neutron Scattering Data for Polycrystalline Aluminium,” May 2006.
M. Mattes, J. Keinert, “Evaluation and Validation of Thermal Neutron Scattering Data for Liquid Natural Argon at 87 K,” IKE, Universitaet Stuttgart, November 2006.
M. Mattes, “ACE File Plots for Hydrogen in Polyethylene,” IKE, Univeristaet Stuttgart, Germany.
The data libraries and documents cited above in Section 10.a are transmitted on DVD, which includes data libraries in ENDF and ACE format and XDIR files. Uncompressed files are about 340 MB.
May 2012.
KEYWORDS: MCNP FORMAT; NEUTRON CROSS SECTIONS