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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-1707/03 Tested 18-MAY-2006

Machines used:

Package ID Orig. computer Test computer
NEA-1707/03 UNIX W.S. PC Windows
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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.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%     
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.

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
NEA-1707/03
Corrections were made to the continuous inelastic scattering matrices (MT=91), for all nuclides for which this chanel is open. This replaces the previous version.
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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-1707/03 18-MAY-2006 Tested at NEADB
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10. REFERENCES
NEA-1707/03, 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-1707/03
MATXS library based on JENDL-3.3
bbcall.bat DOS command procedure prepared at NEA-DB to call TRANSX2/BBC code
(conversion to binary)
readme_matxs-j33.txt Information on the library
update.txt Information on the library (modified MT91 matrices)
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.