RSICC DATA PACKAGE DLC-258

 

 

1.         NAME AND TITLE OF DATA LIBRARY

MATXSLIBJ33 - JENDL-3.3 Based, 175 N-42 Photon Groups (VITAMIN-J) MATXS Library for Discrete Ordinates Multi-Group.

 

2.         NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

NJOY-99.67 and TRANSX-2.15.

 

3.         CONTRIBUTOR

Japan Atomic Energy Research Institute through the OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France. 

 

4.         HISTORICAL BACKGROUND AND INFORMATION

JENDL-3.3 based, 175 neutron-42 photon groups (VITAMIN-J) MATXS library for discrete ordinates multi-group transport codes.

 

History of updates
==================
October 25, 2012
================
Scattering matrices for Pu-239 contained in the 2006 version were incorrect. The whole Pu-239 data were replaced with the calculations obtained by using NOY99.364.

April 3, 2006
=============
Corrections were made for scattering matrices of MT=91.

Dec. 4, 2003
============
The original JENDL-3.3 has two problems in Am-241 data. One is the missing of MF/MT=4/18, and the other is incorrect neutron spectra for MT=18 below 500 keV.

The updated data were produced as JENDL-3.3u. This version of matxslib-j33 reflected the modifications.

 

5.         APPLICATION OF THE DATA

FORMAT: MATXS
NUMBER OF GROUPS: 175 neutron, 42 gamma-ray
Nuclides: 337 nuclides contained in JENDL-3.3

H-1, H-2, He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-Nat, N-14, N-15, O-16, F-19, Na-23, Mg-24, Mg-25, Mg-26, Al-27, Si-28, Si-29, Si-30, P-31, S-32, S-33, S-34, S-36, Cl-35, Cl-37, Ar-40, K-39, K-40, K-41, Ca-40, Ca-42, Ca-43, Ca-44, Ca-46, Ca-48, Sc-45, Ti-46, Ti-47, Ti-48, Ti-49, Ti-50, V-Nat, Cr-50, Cr-52, Cr-53, Cr-54, Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Co-59, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Cu-63, Cu-65, Ga-69, Ga-71, Ge-70, Ge-72, Ge-73, Ge-74, Ge-76, As-75, Se-74, Se-76, Se-77, Se-78, Se-79, Se-80, Se-82, Br-79, Br-81, Kr-78, Kr-80, Kr-82, Kr-83, Kr-84, Kr-85, Kr-86, Rb-85, Rb-87, Sr-86, Sr-87, Sr-88, Sr-89, Sr-90, Y-89, Y-91, Zr-90, Zr-91, Zr-92, Zr-93, Zr-94, Zr-95, Zr-96, Nb-93, Nb-94, Nb-95, Mo-92, Mo-94, Mo-95, Mo-96, Mo-97, Mo-98, Mo-99, Mo-100, Tc-99, Ru-96, Ru-98, Ru-99, Ru-100, Ru-101, Ru-102, Ru-103, Ru-104, Ru-106, Rh-103, Rh-105, Pd-102, Pd-104, Pd-105, Pd-106, Pd-107, Pd-108, Pd-110, Ag-107, Ag-109, Ag-110m, Cd-106, Cd-108, Cd-110, Cd-111, Cd-112, Cd-113, Cd-114, Cd-116, In-113, In-115, Sn-112, Sn-114, Sn-115, Sn-116, Sn-117, Sn-118, Sn-119, Sn-120, Sn-122, Sn-123, Sn-124, Sn-126, Sb-121, Sb-123, Sb-124, Sb-125, Te-120, Te-122, Te-123, Te-124, Te-125, Te-126, Te-127m, Te-128, Te-129m, Te-130, I-127, I-129, I-131, Xe-124, Xe-126, Xe-128, Xe-129, Xe-130, Xe-131, Xe-132, Xe-133, Xe-134, Xe-135, Xe-136, Cs-133, Cs-134, Cs-135, Cs-136, Cs-137, Ba-130, Ba-132, Ba-134, Ba-135, Ba-136, Ba-137, Ba-138, Ba-140, La-138, La-139, Ce-140, Ce-141, Ce-142, Ce-144, Pr-141, Pr-143, Nd-142, Nd-143, Nd-144, Nd-145, Nd-146, Nd-147, Nd-148, Nd-150, Pm-147, Pm-148, Pm-148m, Pm-149, Sm-144, Sm-147, Sm-148, Sm-149, Sm-150, Sm-151, Sm-152, Sm-153, Sm-154, Eu-151, Eu-152, Eu-153, Eu-154, Eu-155, Eu-156, Gd-152, Gd-154, Gd-155, Gd-156, Gd-157, Gd-158, Gd-160, Tb-159, Er-162, Er-164, Er-166, Er-167, Er-168, Er-170, Hf-174, Hf-176, Hf-177, Hf-178, Hf-179, Hf-180, Ta-181, W-182, W-183, W-184, W-186, Hg-196, Hg-198, Hg-199, Hg-200, Hg-201, Hg-202, Hg-204, Pb-204, Pb-206, Pb-207, Pb-208, Bi-209, Ra-223, Ra-224, Ra-225, Ra-226, Ac-225, Ac-226, Ac-227, Th-227, Th-228, Th-229, Th-230, Th-232, Th-233, Th-234, Pa-231, Pa-232, Pa-233, U-232, U-233, U-234, U-235, U-236, U-237, U-238, Np-235, Np-236, Np-237, Np-238, Np-239, Pu-236, Pu-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Pu-244, Pu-246, Am-241, Am-242, Am-242m, Am-243, Am-244, Am-244m, Cm-240, Cm-241, Cm-242, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cm-248, Cm-249, Cm-250, Bk-247, Bk-249, Bk-250, Cf-249, Cf-250, Cf-251, Cf-252, Cf-254, Es-254, Es-255, Fm-255

TEMPERATURES: 300 K
ORIGIN: JENDL-3.3
WEIGHTING SPECTRUM: -- iwt=11 for NJOY-99
LEGENDRE EXPANSION: P6
THERMAL SCATTERING: free gas model
SELF SHIELDING: sigma-0, infinity, 10000, 1000, 300, 100, 30, 10, 1, 0.1, 1.E-5
KERMA factors are provided.

 

6.         SOURCE AND SCOPE OF DATA

Accuracy of pointwise cross-section reconstruction: 0.1%
Upper limit of thermal region: 4.6 eV.

           

7.         DISCUSSION OF THE DATA RETRIEVAL PROGRAM

The nuclear data processing system NJOY-99.67 was used to produce MATXSLIBJ33. It can be further processed using TRANSX-2.15.

 

8.         DATA FORMAT AND COMPUTER

Unix Workstation (D00258MNYCP01). 

 

9.         TYPICAL RUNNING TIME

N/A

 

10.       REFERENCES

Included Documentation:

K. Kosako, N. Yamano, T. Fukahori, K. Shibata and A. Hasegawa: “The Libraries FSXLIB and MATXSLIB Based on JENDL-3.3,” JAERI-Data/Code 2003-011 (July 2003).

 

11.       CONTENTS OF LIBRARY

The MATXSLIBJ33 data files and documentation are transmitted on CD.   

 

12.       DATE OF ABSTRACT

November 2013.

 

KEYWORDS:     CROSS SECTIONS, EVALUATED DATA, MULTI-GROUP, NEUTRON CROSS SECTIONS