last modified: 30-APR-1997 | catalog | categories | new | search |

DLC-0184 ZZ-VITAMIN-B6.

ZZ VITAMIN-B6, Fine-Group Cross-Section Library from ENDF/B-VI.3 for Radiation Transport

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-VITAMIN-B6.
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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-VITAMIN-B6 DLC-0184/01 Tested 30-APR-1997

Machines used:

Package ID Orig. computer Test computer
DLC-0184/01 Many Computers DEC ALPHA W.S.
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3. DESCRIPTION OF PROGRAM OR FUNCTION


%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
FORMAT: AMPX

NUMBER OF GROUPS: 199 neutron and 42 gamma-ray groups

MATERIALS: H1(H2O), H1(CH2), H2(D2O), H3, He3, He4, Li6, Li7, Be9, Be9(thermal), B10, B11, C, C(Graphite), N14, N15, O16, O17, F19, Na23, Mg, Al27, Si, P31, S, S32, Cl, K, Ca, Ti, V, Cr50, Cr53, Cr54, Mn55, Fe54, Fe56, Fe57, Fe58, Co59, Ni58, Ni60, Ni61, Ni62, Ni64, Cu63, Cu65, Ga, Y89, Zr, Zirc-2, Nb93, Mo, Ag107, Ag109, Cd, In, Sn, Eu151, Eu152, Eu153, Eu154, Eu155, Hf174, Hf176, Hf177, Hf178, Hf179, Hf180, Ba138, Ta181, Ta182, W, W182, W184, W186, Re185, Re187, Au197, Pb206, Pb207, Pb208, Bi209, Th230, Th232, Pa231, Pa233, U232, U233, U234, U235, U236, U237, U238, Np237, Np238, Np239, Pu237, Pu238, Pu239, Pu240, Pu241, Pu242, Pu243, Pu244, Am241, Am242, Am242m, Am243, Cm241, Cm242, Cm243, Cm244. Cm245, Cm246, Cm247, Cm248.

ORIGIN: ENDF/B-VI; LENDL for Sn; ENDF/B-IV for Zirc-2

WEIGHTING SPECTRUM:
From 10-5 ev to 0.125 eV     -> Maxwellian Thermal Spectrum
From 0.125 eV to 820.8 keV   -> "1/E" Slowing-Down Spectrum
From 820.8 keV to 20.0 MeV   -> Fission Spectrum

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The successful use of DLC-0041/ZZ-VITAMIN-C, which was based on ENDF/B-IV, and DLC-0113/ZZ-VITAMIN-E, which was based on ENDF/B-V, to a variety of radiation transport problems led to the development  of specifications for ZZ-VITAMIN-B6.
This new multigroup cross-section library based on ENDF/B-VI Release 3 data was produced and tested for light water reactor shielding and reactor pressure vessel dosimetry applications. Significant benchmark data testing of ZZ-VITAMIN-B6 was an integral  part of this development work to accelerate the qualification. Over  50 Benchmarks were calculated using the ZZ-VITAMIN-B6 library. In general, results using the new data show significant improvements relative to earlier ENDF data.
The successful application of ZZ-VITAMIN-B6 to LWR pressure vessel  fluence calculations has been demonstrated. It is expected that the  range of applications will be similar to previous multigroup cross section development efforts using the VITAMIN concept (generation of fine-group, pseudo problem-independent data). In the past, the VITAMIN concept has proven to be a very effective approach for fusion reactor neutronics, LMFBR core physics analysis, radiation effects of nuclear weapons, and light water reactor shielding and dosimetry. This new fine-group, pseudo problem- independent, cross-section library contains 120 nuclides. Several dosimetry response functions and kerma factors for all 120 nuclides are also included with the library. Unlike previous VITAMIN series data libraries, ZZ-VITAMIN-B6 contains multigroup cross sections with thermal upscattering.
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4. METHOD OF SOLUTION

ZZ-VITAMIN-B6 is derived from ENDF/B-VI nuclear data, except for two nuclides (Sn obtained from LENDL and Zirc2 obtained from ENDF/B-IV). The responses and kerma factors were also  derived primarily from ENDF/B-VI. The ENDF data were processed with  the PSR-0355/NJOY94 code system and converted to AMPX master library format with the SMILER module of PSR-0315/AMPX77.
The actual 199 neutron group boundaries in ZZ-VITAMIN-B6 were selected from 175 groups in VITAMIN-J (a European library based on the VITAMIN-C and VITAMIN-E structures) and the 27 groups used in the SCALE shielding library, with deference given to the VITAMIN-J boundaries at higher energies when the energy values are slightly different. The thermal energy range, which contains 36 neutron groups, is defined with 5.043 eV as the uppermost boundary.
The photon energy group structure is based on a combination of the  42 gamma-ray groups in VITAMIN-J and the 18 groups in the SCALE shielding library. The top energy group extends to 30 MeV, which allows proper representation of high energy gamma rays from neutron  capture at high energies. Although the cross-section for capture at  neutron energies between 20 and 30 MeV is small, such a reaction in  some materials could produce gamma rays with energies between 20 and 30 MeV (VITAMIN-E gamma-ray groups only went up to 20 MeV).
  Tables provide information on file contents.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME

Run times are problem dependent. The test cases were run at RSICC on an IBM RS/6000 using modules from the SCAMPI package. The ctrb6 case ran in about 4 minutes. The zpr1 case ran in about 5 minutes, and the zpr2 case ran in about 10 minutes.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

Modules from PSR-0352/SCAMPI, which is a subset of PSR-0315/AMPX77 with some improvements from CCC-0545/SCALE/4.3, were used to read the ASCII files, convert them  to binary, and run test cases. The AIM program, which is included in each of these three packages, reads the formatted data and writes them as unformatted records.
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9. STATUS
Package ID Status date Status
DLC-0184/01 30-APR-1997 Screened
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10. REFERENCES

- D.T. Ingersoll et al.:
  Production and Testing of the VITAMIN-B6 Fine-Group and the
  BUGLE-93 Broad-Group Neutron/Photon Cross-Section Libraries
  Derived from ENDF/B-VI Nuclear Data
  ORNL-6795, NUREG/CR-6214 (January 1995)
DLC-0184/01, included references:
- RSICC:
  READ.ME (December 1996)
- J.E. White et al.:
  VITAMIN-B6: A Fine-Group Cross Section Library Based on ENDF/B-VI
  for Radiation Transport Applications,
  from Proceeding of the International Conference on Nuclear Data
  for Science and Technology, Gatlinburg, Tennessee, pp.733-736
  (May 1994)
- J.E. White et al.:
  BUGLE-96: A Revised Multigroup Cross Section Library for LWR
  Applications Based on ENDF/B-VI Release 3,
  (presented at the Amercian Nuclear Society Radiation Protection
  & Shielding Topical Meeting, April 21-25, 1996, Falmouth, MA)
  (April 1996)
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11. MACHINE REQUIREMENTS

DLC-184/01: The packaged files were installed at the NEA Data Bank on a DEC 3000 Model 300x Alpha Workstation. The ASCII library files  require about 200,Bytes of disk space.
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by:
                Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.

Developed by:
                Oak Ridge National Laboratory,
                Oak Ridge, Tennessee, U.S.A.
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16. MATERIAL AVAILABLE
DLC-0184/01
File name File description Records
DLC0184_01.001 Information file of library ZZ-VITAMIN-B6 423
DLC0184_01.002 Auxiliary C-shell script for installation 182
DLC0184_01.003 RSIC Notes on ZZ-VITAMIN-B6 29
DLC0184_01.004 RSIC Notes on ZZ-VITAMIN-B6, CD-ROM distrib. 42
DLC0184_01.005 Library file # 1 15280
DLC0184_01.006 Library file # 2 18687
DLC0184_01.007 Library file # 3 48522
DLC0184_01.008 Library file # 4 48567
DLC0184_01.009 Library file # 5 40281
DLC0184_01.010 Library file # 6 6106
DLC0184_01.011 Library file # 7 18771
DLC0184_01.012 Library file # 8 21045
DLC0184_01.013 Library file # 9 28765
DLC0184_01.014 Library file # 10 35263
DLC0184_01.015 Library file # 11 24148
DLC0184_01.016 Library file # 12 8390
DLC0184_01.017 Library file # 13 14927
DLC0184_01.018 Library file # 14 20754
DLC0184_01.019 Library file # 15 16873
DLC0184_01.020 Library file # 16 15865
DLC0184_01.021 Library file # 17 22855
DLC0184_01.022 Library file # 18 8958
DLC0184_01.023 Library file # 19 24640
DLC0184_01.024 Library file # 20 17173
DLC0184_01.025 Library file # 21 13941
DLC0184_01.026 Library file # 22 14820
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DLC0184_01.028 Library file # 24 15047
DLC0184_01.029 Library file # 25 12680
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DLC0184_01.031 Library file # 27 12737
DLC0184_01.032 Library file # 28 16549
DLC0184_01.033 Library file # 29 24368
DLC0184_01.034 Library file # 30 16613
DLC0184_01.035 Library file # 31 20887
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DLC0184_01.040 Library file # 36 17931
DLC0184_01.041 Library file # 37 11142
DLC0184_01.042 Library file # 38 15003
DLC0184_01.043 Library file # 39 10662
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DLC0184_01.046 Library file # 42 18833
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DLC0184_01.064 Library file # 60 17864
DLC0184_01.065 Library file # 61 47467
DLC0184_01.066 Library file # 62 44603
DLC0184_01.067 Library file # 63 39178
DLC0184_01.068 Library file # 64 34190
DLC0184_01.069 Library file # 65 8649
DLC0184_01.070 Library file # 66 30504
DLC0184_01.071 Library file # 67 16103
DLC0184_01.072 Library file # 68 21284
DLC0184_01.073 Library file # 69 21814
DLC0184_01.074 Library file # 70 20908
DLC0184_01.075 Library file # 71 22331
DLC0184_01.076 Library file # 72 17976
DLC0184_01.077 Library file # 73 14373
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DLC0184_01.079 Library file # 75 33735
DLC0184_01.080 Library file # 76 6079
DLC0184_01.081 Library file # 77 13806
DLC0184_01.082 Library file # 78 29108
DLC0184_01.083 Library file # 79 19906
DLC0184_01.084 Library file # 80 10819
DLC0184_01.085 Library file # 81 16717
DLC0184_01.086 Library file # 82 12233
DLC0184_01.087 Library file # 83 27651
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DLC0184_01.097 Library file # 93 12529
DLC0184_01.098 Library file # 94 15566
DLC0184_01.099 Library file # 95 12368
DLC0184_01.100 Library file # 96 15623
DLC0184_01.101 Library file # 97 35871
DLC0184_01.102 Library file # 98 10125
DLC0184_01.103 Library file # 99 26484
DLC0184_01.104 Library file # 100 8617
DLC0184_01.105 Library file # 101 14520
DLC0184_01.106 Library file # 102 11772
DLC0184_01.107 Library file # 103 17615
DLC0184_01.108 Library file # 104 18114
DLC0184_01.109 Library file # 105 18187
DLC0184_01.110 Library file # 106 15871
DLC0184_01.111 Library file # 107 14095
DLC0184_01.112 Library file # 108 16682
DLC0184_01.113 Library file # 109 36837
DLC0184_01.114 Library file # 110 25577
DLC0184_01.115 Library file # 111 12034
DLC0184_01.116 Library file # 112 30559
DLC0184_01.117 Library file # 113 26340
DLC0184_01.118 Library file # 114 27043
DLC0184_01.119 Library file # 115 26725
DLC0184_01.120 Library file # 116 27150
DLC0184_01.121 Library file # 117 27814
DLC0184_01.122 Library file # 118 38097
DLC0184_01.123 Library file # 119 15034
DLC0184_01.124 Library file # 120 12172
DLC0184_01.125 Library file # 121 15924
DLC0184_01.126 Neutron response functions in fine-groupe 2150
DLC0184_01.127 Input file (sample problem CTR) 132
DLC0184_01.128 Output file(sample problem CTR) 15432
DLC0184_01.129 Message/error logging file (problem CTR) 6
DLC0184_01.130 Input file (sample problem ZTR part 1) 163
DLC0184_01.131 Output file(sample problem ZPR part 1) 23646
DLC0184_01.132 Message/Error logging file (problem ZPR 1) 8
DLC0184_01.133 Input file (sample problem ZPR part 2) 26
DLC0184_01.134 Output file(sample problem ZPR part 2) 6968
DLC0184_01.135 Message/Error logging file (problem ZPR 2) 2
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17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • Z. Data.

Keywords: cross sections, data library, multigroup.