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