RSICC Home Page CRYO-S(A,B)-ACE1

RSICC DATA PACKAGE DLC-253

1.         NAME AND TITLE OF DATA LIBRARY

CRYO-S(A,B)-ACE1 - Scattering Law and Continuous Energy Cross Section Library of Materials at Cryogenic Temperatures.

2.         NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

NJOY99, MCNP5, MCNPX

3.         CONTRIBUTOR

Universitaet Stuttgart, Institut fuer Kernenergetik und Energiesysteme, Stuttgart, Germany through the Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France.

4.         HISTORICAL BACKGROUND AND INFORMATION

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.

6.         SOURCE AND SCOPE OF DATA

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)

7.         DISCUSSION OF THE DATA RETRIEVAL PROGRAM

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.

8.         DATA FORMAT AND COMPUTER

UNIX workstation, PC, or Mac (D00253MNYCP00).

9.         TYPICAL RUNNING TIME

N/A

10.        REFERENCES

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.

11.        CONTENTS OF LIBRARY

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.

12.        DATE OF ABSTRACT

May 2012.

KEYWORDS:       MCNP FORMAT; NEUTRON CROSS SECTIONS