1. NAME AND TITLE OF DATA LIBRARY

JSD-120: Infinitely Dilute Neutron Multigroup (100) Cross Sections and Coupled Neutron (100) and Gamma-Ray (20) Effective Multigroup Cross Sections for Use in LWR and LMFBR Shield Design and Analysis.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

No retrieval program is in the package.

3. CONTRIBUTOR

Japan Atomic Energy Research Institute, Tokai Research Establishment, Japan.

4. HISTORICAL BACKGROUND AND INFORMATION

JSD-120 is a library of infinite dilute 100 energy group cross sections generated from ENDF/B-IV nuclear data libraries by using the code system RADHEAT-V3. In the energy region above 0.4 MeV, a fission spectrum was used as a weighting function; 1/E-function was used in lower energy below 0.4 MeV. The energy-group structure coincides with that of the DLC-2/100G library for the top 99 groups and group 100 was a thermal group in which a Maxwellian distribution at 20C was assumed.

5. APPLICATION OF THE DATA

Neutron and gamma-ray transport calculations can be performed with the JSD-120 library in which coupled 100 neutron and 20 gamma-ray effective group constants for material typically considered for use in reactor core, structures, and shields are filed in the standard ANISN format. By using the constants, shielding analyses and designs are performed by multigroup discrete ordinates codes or Monte Carlo codes taking into consideration anisotropic scattering expansion up to a P5 approximation. The elastic scattering anisotropy of these cross sections is expanded up to the fifth order of Legendre polynomials; neutron capture cross section is separated to (n,gamma), (n,p), and (n,alpha) reaction cross sections to obtain neutron-induced gamma-ray yields corresponding to each reaction of those described.

6. SOURCE AND SCOPE OF DATA

JSD-120 is a library of a coupled 100 neutron and 20 gamma-ray effective multigroup constants for materials typically considered for use in reactor core, structure and shield. The resonance self-shielding factors given in f-table of JAERI-Fast set have been introduced into the infinite dilution cross sections filed in JSD-100 in order to produce reasonable and accurate effective cross sections of homogenized materials in resonance energy regions. The secondary gamma-ray production cross sections are generated from the effective microscopic neutron cross sections for homogenized materials and the yield data of POPOP4 library. The gamma-ray energy-group structure was chosen from that of EURLIB.

The library contains data for:

H, C, N, O, Na, Mg, Al, Si, K, Ca, Cr, Mn, Fe, Ni, Cn, Zr, Mo, Cd, Pb, 10B, 234U, 235U, 236U, 238U, 237Np, 238Pu, 239Pu, 240Pu and 241Pu for shield coolant,

structure and fuel elements and

6Li, 7Li, F, 27Al, 54Fe, 56Fe, 59Co, 58Ni, 115In and 197Au for detectors.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

Not applicable.

8. DATA FORMAT AND COMPUTER

EBCDIC card images; FACOM 230-75.

9. TYPICAL RUNNING TIME

Step II on RADHEAT-V3 requires approximately 1 minute on the FACOM 230/75 to produce the effective macroscopic cross sections of homogenized mixture constructed by 3 elements from this library.

10. REFERENCES

"Hierarchy of the Code System RADHEAT V3," Chart.

K. Koyama, Y. Okumura, K. Furuta, and S. Miyasaka, Multi-Group Cross Section Sets for Shield Materials, JAERI-M 7291, Reactor Engineering Division Annual Report, pp. 91-92 (April 1, 1977 - March 31, 1977).

TAPEMAKER: RADHEAT V3, A Code System for Generating Coupled Neutron and Gamma-Ray Group Constants and Analyzing Radiation Transport, JAERI-M 7155, pp. 37-40 (1977).

11. CONTENTS OF LIBRARY

Included are the referenced documents and a reel of magnetic tape which contains the JSD-100 and JSD-120 cross section files, the TAPEMAKER Source, and input data to convert the JSD-100 and JSD-120 files to binary mode, plus output lists for the above data; total records 129,533.

12. DATE OF ABSTRACT

December 1977; updated November 1982, December 1984.