RSICC DATA LIBRARY DLC-122

 

1.   NAME AND TITLE OF DATA LIBRARY

JENDL-2 Rev1:  Japanese Evaluated Neutron Cross Section Data in ENDF/B-IV Format.

 

2.   NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

Any programs which can treat evaluated data in the ENDF/B-IV format.

 

3.   CONTRIBUTOR

Japan Atomic Energy Research Institute, Tokai-mura, Japan.

 

4.   HISTORICAL BACKGROUND AND INFORMATION

The first version of Japanese Evaluated nuclear Data Library, JENDL-1, was released in 1977.  The data for 72 nuclides which are important for fast reactor calculation were evaluated and compiled in the ENDF/B-IV format.  The aim of the second version is extended also to the thermal and fusion reactors, and to the shielding problems.  The general purpose file of JENDL-2 contains the data of 89 nuclides.  The data for 92 fission product nuclides will be released in the near future.

 

5.   APPLICATION OF THE DATA

Fast, thermal and fusion reactor calculations and shielding problems.

 

6.   SOURCE AND SCOPE OF DATA

Evaluation was made by members of Japanese Nuclear Data Committee (JNDC).  A brief description of the evaluation for each nuclide is given in a comment part of the data and in Ref.1.  The JENDL-2 file contains the cross sections, angular and energy distributions for the emitted neutrons.  The incident neutron energy ranges from 10^-5 eV to 20 MeV.  For most of the nuclides, the cross sections in the low energy region are represented by means of the resonance parameters.  The multi-level Briet-Wigner formula is adopted for many nuclides even in the case where the spin values are not given exactly.  Pointwise cross section, therefore, must be calculated with a data processing code RESENDD²⁾ which can calculate the resonance cross sections with an approximation given in Ref.2.  The pointwise cross-section data generated with RESENDD are also available.

 

7.   DISCUSSION OF THE DATA RETRIEVAL PROGRAM

Any codes which treat the ENDF/B-IV format can be used as data retrieval programs.  It should be noted, however, the RESENDD ²⁾ must be used to obtain the pointwise cross sections in the resonance regions (see Item 6).

 

8.   DATA FORMAT AND COMPUTER

EBDIC card images, FACOM-M380 (RSICC ID: D00122FM38000).

 

9.   TYPICAL RUNNING TIME

N/A

 

10.  REFERENCES

a.   Documentation available with library

T. Nakagawa (ed.), “Summary of JENDL-2 General Purpose File,” JAERI-M 84-104 (1984).

 

b.   Other useful documentation

T. Nakagawa, “Program RESENDD (Version 84-07):  Program for Reconstruction of Resonance cross Sections from Evaluated Nuclear Data in the ENDF/B Format,” JAERI-M 84-192 (1984).

 

 

11.  CONTENTS OF LIBRARY

The package is transmitted on a CD which contains the referenced document in 10.a and a compressed Unix tar file including the ASCII data.

 

12.  DATE OF ABSTRACT

November 1986.

 

KEYWORDS:   EVALUATED NEUTRON CROSS SECTIONS