RSICC DATA PACKAGE DLC-238

 

1.   NAME AND TITLE OF DATA LIBRARY

            VITENEA-J: AMPX 175-n,42-g Multigroup X-section Library for Nuclear Fusion Applications.

 

2.   NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

AIM: Convert AMPX master card-image data to binary format. AIM is not included but is distributed in AMPX, SCALE and SCAMPI packages.

 

3.   CONTRIBUTOR

ENEA – FIS-MET, Bologna, Italy, and Bologna University, Physics Department, Italy, through the OECD Nuclear Energy Agency Data Bank, Issy-Les Molineaux, France.

 

4.   HISTORICAL BACKGROUND AND INFORMATION

VITENEA-J is a coupled multigroup cross section library in the standard VITAMIN-J energy group structure (175 neutron + 42 gamma) in AMPX master library format produced by ENEA-Bologna for nuclear fusion applications.

 

5.   APPLICATION OF THE DATA

This library has been widely used by ENEA group in neutron/gamma transport calculations for ITER safety assessment via the SCALENEA-1 multipurpose Sn calculation sequence.

 

6.   SOURCE AND SCOPE OF DATA

It is based on nuclear data from the general purpose Fusion Evaluated Nuclear Data Library (FENDL/E-2.0) and ENDF-B/VI. The data were prepared by processing basic nuclear data into a fine group problem independent format through an automatic calculation procedure using the modules of NJOY-94.105 and AMPX-77 Processing Systems. The translation of the multigroup data from the GENDF format produced by NJOY to the AMPX Master Library format was performed by means of the AMPX-77 SMILER module.

The library contains 75 nuclides. Seventy nuclides were processed at four temperatures (300 K, 600 K, 900 K, 1500 K) at ten values for the background cross section s0. Thermal scattering cross sections were processed at the three temperatures (296 K, 600 K, 1200 K) available in the ENDF-B/VI thermal scattering law data file for four additional bound nuclides (H-1 in water, C in graphite, Be in beryllium metal and oxide).

The material characterized by MAT=900 has been added in the library. It contains the ANSI standard neutron/gamma flux to dose rate factors, in the 175n and 42 gamma group structure, to be used for dose rate calculations.

 

List of the included materials:

1-H-1                1-H-1(water)           1-H-2

1-H-3                2-He-3                    2-He-4

3-Li-6               3-Li-7                     4-Be-9

4-Be-9(metal)     4-Be-9(oxide)           5-B-10

5-B-11              C–nat                      C-nat(graphite)

7-N-14              7-N-15                    8-O-16

9-F-19              11-Na-23                 Mg-nat

13-Al-27            14-Si-28                  14-Si-29

14-Si-30            15-P-31                   S-nat

Cl-nat                K –nat                     Ca-nat

Ti-nat                23-V-51                  24-Cr-50

24-Cr-52           24-Cr-53           24-Cr-54

25-Mn-55          26-Fe-54           26-Fe-56

26-Fe-57           26-Fe-58           27-Co-59

28-Ni-58           28-Ni-60           28-Ni-61

28-Ni-62           28-Ni-64           29-Cu-63

29-Cu-65           Ga-nat               Zr-nat

41-Nb-93          Mo-nat              Cd-nat

Sn-nat               Hf-nat               72-Hf-176

72-Hf-177         72-Hf-178         72-Hf-179

72-Hf-180         73-Ta-181         W-nat

74-W-182          74-W-183          74-W-184

74-W-186          79-Au-197         82-Pb-206

82-Pb-207         82-Pb-208         83-Bi-209

47-Ag-107         47-Ag-109         ANSI-Flux

 

7.   DISCUSSION OF THE DATA RETRIEVAL PROGRAM

The library is in AMPX Master Library fido free format. It is suitable for direct use in the AMPX, SCALE and SCAMPI Systems. The library has been checked with the SCAMPI module RADE and translated to binary format with AIM. The output of the ALE module is included which lists the main features of the library.

 

8.   DATA FORMAT AND COMPUTER

Card images in AMPX master library format; all computers (D00238/MNYCP/00).

This is the same package that the NEADB distributes as NEA-1703/01.

 

9.   TYPICAL RUNNING TIME

Not applicable.

 

10.  REFERENCES

a.   Documentation available with library

D.G. Cepraga , M. Frisoni, G. Cambi, “VITENEA-J: A Multigroup Coupled (175n-42gamma) Cross Section Library in AMPX Format for Nuclear Fusion Applications.” RTI/FIS/MET/2004/2

b.   Other useful documentation

D.G.Cepraga, G.Cambi, F.Carloni, M.Frisoni, D.Ene, “Neutronics and activation calculation for ITER generic site safety report,” Fusion Engineering and design 63-64 (2002) 193-197.

D.G.Cepraga, G.Cambi, M.Frisoni, “The SCALENEA-1 multipurpose Sn calculation sequence for application in fusion field: main features and its validation based on experimental data from a low-level waste repository, 20th IEEE/NPSS Symposium, SOFE 2003, San Diego.”

 

11.  CONTENTS OF LIBRARY

The package is transmitted on a CD-ROM which contains the documentation and the data files distributed in a Unix tar file.

 

12.  DATE OF ABSTRACT

June 2009.

 

KEYWORDS:   AMPX INTERFACE FORMAT; COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; MULTIGROUP CROSS SECTIONS; NEUTRON CROSS SECTIONS