DLC-0041 ZZ-VITAMIN-C/B.

ZZ VITAMIN-C/B, 171 Neutron-Group, 36 Gamma-Group Coupled Cross-Section for Fusion, LMFBR Calculations

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: ZZ-VITAMIN-C/B.

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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-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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3. DESCRIPTION OF PROBLEM OR FUNCTION

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

  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) up to 0.125eV
                      - 1/E slowing down spectrum to 820.8 KeV
                      - fission spectum to 10.0 MeV
                      - 1/E spectrum to 12.57 MeV
- velocity exponential fusion peak to 15.57MeV                       - 1/E spectrum to 17.333 MeV.
Gamma cross sections are flat-weighted.

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
ZZ-VITAMIN-C/B is a data library containing 171 neutron, 36 gamma-ray group cross section data for fusion and LMFBR neutronics.
The weighting function for the neutron data consists of six regions: a Maxwellian thermal spectrum (300K) up to 0.125 eV, a 1/E  slowing down spectrum to 820.8 KeV, a fission spectum to 10.0 MeV, a 1/E spectrum to 12.57 MeV, a velocity exponential fusion peak to 15.57 MeV, and a 1/E spectrum to 17.333 MeV. The gamma cross sections are flat-weighted.
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.

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4. METHOD OF SOLUTION

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.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

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6. TYPICAL RUNNING TIME:

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7. UNUSUAL FEATURES OF THE PROGRAM

The AMPX and CCCC interface formats allow the user to perform self-shielding and group collapsing to format a problem dependent library for his own use.

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8. RELATED AND AUXILIARY PROGRAMS:

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9. STATUS

Package ID	Status date	Status
DLC-0041/02	20-JUL-1992	Screened

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10. REFERENCES:

DLC-0041/02, included references:

- R.W. Roussin, C.R. Weisbin, J.E. White, N.M. Greene, R.Q. Wright,
  J.B. Wright:
  The CTR Processed Multigroup Cross Section Library for Neutronics
  Studies
  ORNL/RSIC-37.
- R.W. Roussin, D.B. Simpson:
  Sample Problems for DLC-41/VITAMIN-C Presented at the RSIC Work
  shop on Multigroup Cross-Section Handling Codes
  (March 1978).

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11. MACHINE REQUIREMENTS:

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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 AUTHOR

Oak Ridge National Laboratory
Oak Ridge
Tennessee 37830, USA

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16. MATERIAL AVAILABLE

DLC-0041/02

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

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17. CATEGORIES

C. Static Design Studies
X. Magnetic Fusion Research
Z. Data.

Keywords: LMFBR reactors, cross sections, data, fusion reactors, gamma spectra, group constants, neutron spectra.