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NEA-1707 ZZ-MATXSLIBJ33.

ZZ MATXSLIBJ33,JENDL-3.3 based,175 N-42 photon groups (VITAMIN-J) MATXS lib. for discrete ordinates multi-group

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1. NAME OR DESIGNATION:  ZZ-MATXSLIBJ33.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
ZZ-MATXSLIBJ33 NEA-1707/04 Arrived 24-SEP-2013

Machines used:

Package ID Orig. computer Test computer
NEA-1707/04 UNIX W.S.
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3. DESCRIPTION OF PROGRAM OR FUNCTION

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

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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.
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4. METHODS

The nuclear data processing system NJOY-99.67 was used to produce MATXSLIBJ33. It can be further processed using TRANSX-2.15.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Accuracy of pointwise cross-section reconstruction: 0.1%
Upper limit of thermal region: 4.6 eV.
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6. TYPICAL RUNNING TIME
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS:  NJOY-99 and TRANSX-2.15.
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9. STATUS
Package ID Status date Status
NEA-1707/04 24-SEP-2013 Masterfiled Arrived
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10. REFERENCES
NEA-1707/04, included references:
- 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)
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11. HARDWARE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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13. SOFTWARE REQUIREMENTS
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

   
K. Kosako(+), N. Yamano(+), T. Fukahori, K. Shibata(*) and A. Hasegawa
Nuclear Data Center
Japan Atomic Energy Research Institute
Tokai-mura, Ibaraki-ken 319-1195, Japan
(*) Corresponding author
(+) Sumitomo Atomic Energy Industries, Ltd.
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16. MATERIAL AVAILABLE
NEA-1707/04
MATXS library based on JENDL-3.3
readme_matxs-j33.txt Information on the library
update.txt history of updates
matxslibj33.pdf Report JAERI-Data/Code 2003-011
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17. CATEGORIES
  • Z. Data.

Keywords: cross sections, evaluated data, multigroup, neutron cross sections.