last modified: 25-JAN-1996 | catalog | categories | new | search |

DLC-0113 ZZ-VITAMIN-E.

ZZ VITAMIN-E, 174-Group Neutron, 38-Group Gamma Cross-Section in AMPX Format

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-VITAMIN-E.
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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-E DLC-0113/01 Tested 25-JAN-1996

Machines used:

Package ID Orig. computer Test computer
DLC-0113/01 IBM 3033 DEC ALPHA W.S.
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3. DESCRIPTION OF PROGRAM OR FUNCTION


%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%

  FORMAT: AMPX

  NUMBER OF GROUPS: 174 neutron and 38 gamma-ray groups

NUCLIDES: H, He, Li, Be, B, C, N, O, F, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Ga, Y, Zr, Nb, Mo, Cd, Sn, I, Cs, Ba, Gd, Hf, Ta, W, Re, Pt, Au, Pb, Bi, Th, Pa, U, Np, Pu, Am, Cm.

  ORIGIN: ENDF/B-V

  WEIGHTING SPECTRUM:
From 10-5 ev to 0.414 eV    -> Maxwellian Thermal Spectrum
From 0.414 eV to 2.12 MeV   -> "1/E" Slowing-Down Spectrum
From 2.12 MeV to 10.0 MeV   -> Fission Spectrum
From 10.0 MeV to 12.52 MeV  -> "1/E" Spectrum
From 12.52 MeV to 15.68 MeV -> Velocity Exponential Fusion Peak
From 15.68 MeV to 19.64 MeV -> "1/E" Spectrum
Photon interaction cross sections  -> constant in energy

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
The early phases of this new cross-section library were focused on materials for fast reactor applications and were applied to benchmark testing of ENDF/B-V. More recently, requests have been made for additional materials to be added to the basic library for fusion and weapons radiation transport applications. The library is expected to perform well for radiation  transport problems where thermal upscatter is not important.
The energy structure of VITAMIN-E contains 174 neutron and 38 gamma-ray groups and includes the 171 neutron and 36 photon groups of VITAMIN-C as a subset. The group structure has fine detail in the energy region where cross section minima occur for important shielding materials.
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4. METHOD OF SOLUTION

The 174 neutron group data were processed with  MINXI5; the 174 neutron, 38 photon group data were processed with LAPHNGAS (AMPX III); and the 38 gamma-ray group data with SMUG (AMPX III) from DLC-99/HUGO. The ENDF/B-V special purpose dosimetry, activation, and gas production files have also been processed into the VITAMIN-E group structure using XLACS2, NITAWL, and WORM.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME

The first part of the ZPR 6/7 infinite medium problem required approximately 55,000 I/O's and 10.5 CPU minutes on  the IBM 3033. This includes the 20,000 I/O's and 9 CPU minutes required to convert the formatted library to binary. The XSDRNPM run required only 37 CPU seconds and 6065 I/O's. and GIP/ANISN run took  10,060 I/O's and 38 CPU seconds. The first part of the CTR standard  blanket run required 58,066 I/O's and 10.15 CPU minutes. The XSDRNPM problem ran for 1.3 CPU minutes using 5147 I/O'S while the GIP/ANISN run required 1.16 CPU minutes and 9160 I/O's.
DLC-0113/01
The package has only been screened by the NEA-DB. No attempt was made to implement it and run the test cases.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

No retrieval program is provided. The PSR-117/MARS or PSR-63/AMPX code packages are suggested for full implementation of the capabilities of VITAMIN-E. JCL and sample input are provided to execute sample problems using MARS.
PSR-117/MARS can be used to translate the data into binary form and to perform a variety of useful manipulations including checking, editing, self shielding, and group collapsing.
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9. STATUS
Package ID Status date Status
DLC-0113/01 25-JAN-1996 Screened
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10. REFERENCES:
DLC-0113/01, included references:
- R.W. Roussin et al.:
  VITAMIN-E - A Coupled 174-Neutron, 38 Gamma-Ray Multigroup Cross
  Section Library for Deriving Application-Dependent Working
  Libraries for Radiation Transport Calculations
  Draft ORNL.RSIC Report (December 1987).
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11. MACHINE REQUIREMENTS:
DLC-0113/01
About 110 Mbytes of disk space are required to hold all files of the package.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
DLC-0113/01 PL/I
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
DLC-0113/01
Several JCL files specific to machines of the family of the IBM-3033 are provided to compile, link, create the executables and run the sample problems.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

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
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16. MATERIAL AVAILABLE
DLC-0113/01
File name File description Records
DLC0113_01.001 Information file of the package VITAMIN-E 395
DLC0113_01.002 Script for installation in UNIX systems 35
DLC0113_01.003 174 N-GROUP X-SECTIONS (16 MATERIALS) 351889
DLC0113_01.004 174 N-GROUP X-SECTIONS (20 MATERIALS) 350993
DLC0113_01.005 174 N-GROUP X-SECTIONS (23 MATERIALS) 242877
DLC0113_01.006 174 N-GROUP X-SECTIONS (21 MATERIALS) 119653
DLC0113_01.007 174 N-GROUP X-SECTIONS ( 5 MATERIALS) 93959
DLC0113_01.008 174 N-GROUP X-SECTIONS ( 4 MATERIALS) 53710
DLC0113_01.009 174 N-GROUP, 38 G-GROUPS (62 MATERIALS) 48549
DLC0113_01.010 38 GROUP PHOTONS INTERACTION LIBRARY 76062
DLC0113_01.011 174 GROUP NEUTRON DOSIMETRY (26 MATERIALS) 2888
DLC0113_01.012 174 GROUP NEUTRON ACTIVATION (53 MATERIALS) 6740
DLC0113_01.013 174 GROUP NEUTRON GAS PROD. (18 MATERIALS) 1296
DLC0113_01.014 JCL to create subroutine library 99
DLC0113_01.015 ALIAS-PL1 source to create subroutine librar 63
DLC0113_01.016 JCL with step 1 of ZPR-6/7 sample problem 178
DLC0113_01.017 JCL with step 2 of ZPR-6/7 prob. via XSDRNPM 71
DLC0113_01.018 JCL with step 2 of ZPR-6/7 prob. via ANISN 107
DLC0113_01.019 JCL with step 1 of CTR blanket problem 269
DLC0113_01.020 JCL with step 2 of CTR prob. via XSDRNPM 71
DLC0113_01.021 JCL with step 2 of CTR prob. via ANISN 154
DLC0113_01.022 Output from step 1 of ZPR sample problem 1732
DLC0113_01.023 Output from step 2 of ZPR problem (XSDRNPM) 911
DLC0113_01.024 Output from step 2 of ZPR problem (ANISN) 1362
DLC0113_01.025 Output from step 1 of CTR sample problem 4979
DLC0113_01.026 Output from step 2 of CTR problem (XSDRNPM) 4894
DLC0113_01.027 Output from step 2 of CTR problem (ANISN) 2462
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17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • X. Magnetic Fusion Research
  • Z. Data.

Keywords: coupled neutron gamma cross sections, data library, fusion reactors, shielding.