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IAEA1397 ZZ-WIMS-D/4LIB.

ZZ WIMS-D/4LIB, 61, 64, 69, 76 and 79 energy groups WIMS-D/4 libraries

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1. NAME OR DESIGNATION:  ZZ-WIMS-D/4LIB contains:
1. ZZ-WIMSUT01/61;
2. ZZ-WIMSUT01/64;
3. ZZ-WIMSUT01/69;
4. ZZ-WIMSUT01/76;
5. ZZ-WIMSUT01/79;
Five WIMS-D/4 libraries in 61,64,69,76 and 79 energy groups, which have the same number of fast and thermal groups but different in resonance group, namely 5, 8, 13, 20, 23. with the same format as for the standard WIMS library. The files were processed from ENDF/B6 using a program developed by the library originators.
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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-WIMS-D/4LIB IAEA1397/01 Arrived 16-OCT-2002

Machines used:

Package ID Orig. computer Test computer
IAEA1397/01 Many Computers
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3. DESCRIPTION

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
  FORMAT: WIMS
  NUMBER OF GROUPS:  61,64,69,76,79 energy groups
  NUCLIDES:
                The following nuclides are included:
H-1, H-1 (in H2O), H-1 (in ZrH), H-2, H-2 (in D2O), He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C, C (in graphite), N-14, 0-16, F, Na, Al, Si, P-31, S-32, K, Ti, V, Cr, Mn-55, Fe, Co-59, Ni, Cu, Cu-63, Zr, Nb-93, Mo, Mo-92, Mo-94, Mo-95, Mo-96, Mo-97, Mo-98, Mo-99, Mo-100, Ag-107, Ag-109, Cd, In-113, In-115, Sn, Gd, Dy-164, Er-166, Er-167, Lu-176, Hf, Hf-174, Hf-176, Hf-177, Hf-178, Hf-179, Hf-180, Ta-181, Au-197, Pb.

                The following fission products are included:
Kr-83, Mo-95, Tc-99, Ru-101, Ru-103, Rh-103, Rh-105, Pd-105, Pd-108, Ag-109, Cd-113, In-115, I-127, I-135, Xe-131, Xe-135, Cs-133, Cs-134, Cs-135, Nd-143, Nd-145, Pm-147, Pm-148g, Pm-148m, Pm-149, Sm-147, Sm-148, Sm-149, Sm-150, Sm-151, Sm-152, Eu-153, Eu-154, Eu-155, Gd-157, Pseudo F.P., Dummy ID = 237 Abs. XS = 1.0E-5 B

                The following actinides are included:
Th-232, Pa-233, U-233, U234, U-235, U-236, U-237, U-238, Np-237, Np-238, Np-239, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-242g, Am-242m, Am-243, Cm-242, Cm243, Cm-244, !/v absorber ID = 1000.

  ORIGIN: ENDF/B-V or IV and JENDL-2(Rev.1); and from ENDL-84, where data was not available in ENDF/B.

Neutron cross section library for thermal reactor design analysis with  61, 64, 69, 76, and 79 energy WIMS groups structure.

Group Energy Structure for resonance region:

WIMSUT61              WIMSUT64              WIMSUT69
9118.00-1942.40   9118.00-3522.40       9118.00-5530.00
1942.40-413.770   3522.40-1344.00       5530.00-3319.10
413.770-88.1450   1344.00-526.000       3319.10-2339.45
88.1450-18.7770   526.000-201.090       2339.45-1425.10
18.7770-4.00000   201.090-76.500        1425.10-906.898
                  76.5000-28.1270       906.898-367.262
                  28.1270-10.700        367.262-148.728
                  10.7000-4.00000       148.728-75.5014
                                        75.5014-48.0520
                                        48.0520-27.7000
                                        27.7000-15.9680
                                        15.9680-9.96800
                                        9.96800-4.00000


WIMSUT76               WIMSUT79
9118.00-6724.90    9118.00-6692.50
6724.90-4960.00    6692.50-4112.20
4960.00-3658.30    4912.20-3605.40
3658.30-2698.20    3605.40-2646.30
2698.20-1912.70    2646.30-1945.00
1912.70-1355.70    1945.00-1423.00
1355.70-961.150    1423.00-1043.00
961.150-681.350    1043.00-783.000
681.350-483.000    783.000-561.000
483.000-340.250    561.000-414.30
340.250-241.200    414.300-304.00
241.200-179.100    304.00-222.910
179.10-126.9600    222.910-161.000
126.960-90.000     161.000-124.000
90.0000-63.8000    124.000-86.500
63.80000-44.800    86.500-53.200
44.80000-28.250    53.200-47.4860
28.25000-13.554    47.486-29.560
13.55400-9.4400    29.560-12.500
.9.440000-4.0000   12.500-10.800
                   10.800-8.4700
                   8.4700-4.7900
                   4.7900-4.0000

  WEIGHTING SPECTRUM: Within-group weighting fluxes were computed.
The weighting spectrum is:

4KT>E>0eV ........ (S(E)=E.EXP(-E/(KT))/KT ............Maxwellian

670KeV>E>=4KT......(S(E)=C1/E..........................1/E

10MeV>=E>=670KeV...(S(E)=C2.EXP(-E/Wa).Sinh(E.Wb)^1/2..Fission

KT = 0.025eV; Wa = 9.65E+05; Wb = 2.29E-06

The constants C1 & C2 are defined for continuity of the spectrum function.
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4. METHODS

The library was produced using preprocessing codes to extract data from ENDF/B-VI or and JENDL-2 (Rev.1); and from where data was not available in ENDF/B6.Transport cross sections were computed using P1 scattering matrix data. Within-group weighting fluxes for actinides were computed on an ultra-fine group basis for accurate intermediate resonance self-shielding. A more explicit representation was adapted for the fission-product chain.
A more extensive representation of the actinide burnup chain including Th cycle was selected.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

- The resonance integrals are calculated with GROUPIE, which uses the NR approximation.  The difference relative to the definitions used in the WIMS code are acknowledged. The discrepancies in calculating integral spectral parameters originate to a large extent from these definitions.

- The preparation of the scattering matrix is based on an analytical expression for energy loss and average scattering cross sections.This approach ignores the information on energy and angular distributions in the ENDF files.

- The average cosine of scattering should be calculated from the angular distributions, but instead it is taken from older evaluations, in which this parameter was given explicitly.
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6. TYPICAL RUNNING TIME
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS

WIMS-D/4.
The libraries were constructed without taking advantage of NJOY. For this purpose some programs had to be written.
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9. STATUS
Package ID Status date Status
IAEA1397/01 16-OCT-2002 Masterfiled Arrived
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10. REFERENCES

-  Jung-Do Kim: WIMKAL-88, The 1988 Version of WIMS-KAERI Library
IAEA-NDS-92, Rev. 0 (August 1990)

-  Jung-Do Kim, Jong Tai Lee, Choong-Sup Gil and Hark Rho Kim:
Generation and Benchmarking of a 69-group Cross Section Library for Thermal Reactor Applications ENDF/B6
IAEA1397/01, included references:
- Ali Pazirandeh and Alireza Tabesh:
New WIMS Library Generation from ENDF/B6 and Effect of Resonance
Group Structure on Cell Parameters
International Conference on Nuclear Data for Science and Technology
Oct. 7-12, 2001, Tsukuba International Congress Center,Tsukuba, Ibaraki, Japan
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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

Physics Department,
University of Tehran,
P.O.Box 1943, Tehran 19395, IRAN
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16. MATERIAL AVAILABLE
IAEA1397/01
ATP61.LIB Library
ATP64.LIB Library
ATP69.LIB Library
ATP76.LIB Library
ATP79.LIB Library
WIMSLIBCol.doc Describing paper
WIMSUT01.doc Abstract
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17. CATEGORIES
  • Z. Data.

Keywords: ENDF/B, data library, evaluated data, neutron cross sections, thermal reactors.