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Program name | Package id | Status | Status date |
---|---|---|---|
ZZ-VITAMIN-C | DLC-0041/02 | Tested | 20-JUL-1992 |
Machines used:
Package ID | Orig. computer | Test computer |
---|---|---|
DLC-0041/02 | IBM 360/91 | DEC VAX 8810 |
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FORMAT: AMPX, CCCC format.
NUMBER OF GROUPS: 171 neutron, 36 gamma-ray group cross section
NUCLIDES: H, He, Li, Be, B, C, N, O, F, Na, Mg, Al, Si, P, S, K, Ca, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zr, Nb, Mo, Ag, Cd, Sn, Eu, Ta, W, Pb, Th, U, Pu, Am
ORIGIN: ENDF/B
WEIGHTING SPECTRUM:
Maxwellian thermal spectrum (300K) 10-5 to 0.125eV
1/E slowing-down spectrum 0.125eV to 820.8 KeV
fission spectum 820.8 keV to 10.0 MeV
1/E spectrum 10.0 MeV to 12.57 MeV
velocity exponential fusion peak 12.57 to 15.57 MeV
1/E spectrum 15.57 MeV to 17.333 MeV
Gamma cross sections are flat-weighted.
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ZZ-VITAMIN-C/B is a data library containing 171 neutron, 36 gamma-ray group cross section data for fusion and LMFBR neutronics.
The Legendre expansion order is P3. Data are available in the form of a 171 neutron group AMPX interface, a 171 neutron 36 gamma-ray production AMPX interface, and a 36 group gamma-ray interaction AMPX interface. The neutron data are also available in CCCC format as ISOTXS neutron cross section and BRKOXS self-shielding factor standard interface files.
Data exists for 60 nuclides used in proposed fusion or fission/ fusion hybrid systems.
The data has been computed from ENDF/B files using the program MINX. The Bondarenko method is employed to create group dependent resonance self-shielding factors to account for temperature and dilution effects. The fractional error tolerances were set to 0.5 percent, and 0.1 percent for integration.
File name | File description | Records |
---|---|---|
DLC0041_02.001 | Information file | 70 |
DLC0041_02.002 | 171 neutron group xsecs (21 materials) | 163883 |
DLC0041_02.003 | 36 photon interaction xsecs (42 materials) | 20833 |
DLC0041_02.004 | 171 neutron group xsecs (20 materials) | 185053 |
DLC0041_02.005 | 171 neutron-36 gamma coupled group xsecs | 33005 |
DLC0041_02.006 | 171 neutron group xsecs (25 materials) | 98685 |
DLC0041_02.007 | GIP source program | 1684 |
DLC0041_02.008 | ANISN source program | 4026 |
DLC0041_02.009 | JCL to compile & assemble AMPX-II subr. lib | 31 |
DLC0041_02.010 | JCL & input data for AIM | 29 |
DLC0041_02.011 | JCL & input data for AJAX,BONAMI,RADE,.. | 254 |
DLC0041_02.012 | JCL & input data for GIP & ANISN | 103 |
DLC0041_02.013 | JCL & input data for AIM & CHOX | 93 |
DLC0041_02.014 | JCL & input data for RADE,DIAL,MALOCS | 122 |
DLC0041_02.015 | JCL & input data for NITAWL, XZSDRNPM | 130 |
DLC0041_02.016 | JCL & input data for GIP, ANISN | 84 |
DLC0041_02.017 | Output from AIM (BCD AMPX) | 66 |
DLC0041_02.018 | Output from AJAX | 77 |
DLC0041_02.019 | Output from BONAMI | 2415 |
DLC0041_02.020 | Output from RADE | 857 |
DLC0041_02.021 | Output from NITAWL (see file 14) | 240 |
DLC0041_02.022 | Output from XSDRNPM | 904 |
DLC0041_02.023 | Output from GIP | 293 |
DLC0041_02.024 | Output from ANISN | 991 |
DLC0041_02.025 | Output from AIM (BCD AMPX LAPHNGAS) | 66 |
DLC0041_02.026 | Output from AIM (BCD AMPX SMUG) | 66 |
DLC0041_02.027 | Output from CHOX | 92 |
DLC0041_02.028 | Output from RADE | 972 |
DLC0041_02.029 | Output from DIAL | 1359 |
DLC0041_02.030 | Output from MALOCS | 436 |
DLC0041_02.031 | Output from NITAWL (see file 25) | 175 |
DLC0041_02.032 | Output from XSDRNPM (CTR standard blanket) | 2255 |
DLC0041_02.033 | Output from GIP (CTR standard blanket) | 248 |
DLC0041_02.034 | Output from ANISN (CTR standard blanket) | 2125 |
Keywords: LMFBR reactors, cross sections, data, fusion reactors, gamma spectra, group constants, neutron spectra.