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RSIC DATA LIBRARY DLC-150

1. NAME AND TITLE OF DATA LIBRARY

VITAMIN-J/KERMA: VITAMIN-J 175-Neutron and 38-Photon Kerma And Gas Production Cross Sections

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

None provided. See format of data library in documentation.

3. CONTRIBUTORS

ENEA, Bologna, Italy, through NEA Data Bank, Gif-sur-Yvette Cedex, France.

4. HISTORICAL BACKGROUND AND INFORMATION The Evaluated File (EFF-1), together with the Joint European File (JEF-1), is rapidly becoming the standard European data source for thermal reactors, fast reactors, fusion, shielding and controlled thermonuclear analysis. JEF is administered by the Nuclear Energy Agency (NEA Data Bank). While processing the EFF-1 data in order to obtain a 175 neutron - 38 gamma group library GEFF-1, gas production cross sections, neutron and photon kerma factors were also computed.

5. APPLICATION OF THE DATA

The cross section data and kerma factors are written in the FOURACES (PSR-183) format and can be used by transport and discrete ordinates codes which can read this format.

6. SOURCE AND SCOPE OF DATA

For the gas production cross sections, the lump reactions 203 to 207 included in EFF-1 were assumed as the basis of the computation. The neutronic kerma factors were calculated through the THEMIS module KERMA. The photonic kerma factors were computed from the DLC-99/HUGO of gamma interaction data through the THEMIS module GROUPG. Some neutronic kerma factors appeared to be doubtful because of threshold values not exactly stated in EFF-1; these data have been discarded.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAMS

Not Applicable.

8. DATA FORMAT AND COMPUTER

Card images; IBM 3090.

9. TYPICAL RUNNING TIME

None noted.

10. REFERENCES

a. Included in the package:

"Format of FOURACES Data File (Taken From RT/FI(73)16, FOUR ACES - A Programme for Producing Group Averaged Cross Sections for Different Files by G. C. Panini)," Informal notes. 1 page.

E. Cuccoli, G. C. Panini. Graphical Presentation of GEFF-1 Scheme Gas Production Cross Sections, JEF/DOC-152, ENEA, Bologna, Italy, October 5, 1986.

E. Cuccoli, G. C. Panini. Graphical Presentation of GEFF-1 Scheme Neutron Kerma Factors, JEF/DOC-150, ENEA, Bologna, Italy, October 5, 1986.

E. Cuccoli, G. C. Panini. Graphical Presentation of GEFF-1 Scheme Gamma Kerma Factors, JEF/DOC-151, ENEA, Bologna, Italy, October 5, 1986.

11. CONTENTS OF PACKAGE

The package contains references listed above, and the data libraries. The data library is transmitted on one DS/HD 3.5" diskette in DOS format.

12. DATE OF ABSTRACT

January 1991.

KEYWORDS: DAMAGE CROSS SECTIONS; KERMA FACTORS; MULTIGROUP CROSS SECTIONS; REACTION CROSS SECTIONS