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NEA-1702 ZZ-VITENEA-E.

ZZ VITENEA-E, AMPX 174-N,38-gamma multigroup X-sec.library for multidimensional radiation transport and dose evaluation

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1. NAME OR DESIGNATION:  ZZ-VITENEA-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-VITENEA-E NEA-1702/01 Tested 25-MAY-2004

Machines used:

Package ID Orig. computer Test computer
NEA-1702/01 RISC 6000 Linux-based PC
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3. DESCRIPTION OF PROGRAM OR FUNCTION

VITENEA-E is a coupled 174-neutron, 38-gamma-ray multigroup cross sections library in AMPX format suitable for multidimensional radiation transport calculations and dose evaluation. To produce that library, the file ENDF/B-VI has been chosen as primary source of basic nuclear data because it is suitable for processing using the NJOY-SMILER-SCALE sequence. That file is adequate for fusion calculations since it allows important features, like:
- data for angle-energy correlation of high energy neutrons, charged particles and recoil nuclei;
- separate isotopic evaluations for the main structural materials;
- photon production data for the main structural materials.
  
The neutron weighting function is taken from Vitamin-E. It has the form:
- Maxwellian thermal spectrum (from 10-5 to 0.414 eV),
- 1/E slowing down region (from 0.414 eV to 2.1225 MeV),
- fission spectrum (from 2.1225 to 10 MeV),
- 1/E (from 10 to 12.52 MeV),
- DT fusion neutron spectrum (from 12.52 to 15.68 MeV)
- 1/E (from 15.68 to 19.64 MeV).
  
The photon weighting spectrum is assumed to be constant both for production from neutron reactions and for interactions among photons only. The scattering Legendre expansion order is assumed to be 8, both for the neutron and the photon interactions.The library is based upon the Bondarenko method for the resonance self-shielding and the temperature effects. The materials were processed at 293.6, 900, 2100 K. Ten values of the background cross sections are considered: 10+10, 1000, 300, 100, 30, 10, 3, 1, 0.1, 10-6.
  
The basic nuclear data (ENDF-B/VI) related to the following materials have been processed and included into VITENEA-E:
H (free gas), H (water), H-3, He-4, Li-6, Li-7, Be-9 (metallic), Be-9 (BeO), C (free gas), C (graphite), O, Al-27, Si,, Ti, Cr-50, Cr-52, Cr-53, Cr-54, Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Co-59, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Cu-63, Cu-65, Mo, Wnat, W-182, W183, W184, W186, Hf-176, Hf-177, Hf-178, Hf-179, Hf-180,Re-187.
Additional materials have been included into the Vitamin-ENEA by taking their multigroup cross sections directly from the Vitamin-E library [1].
They are:
H2, Li-6, Li-7, B-10, B-11, N-14, Na-23, Mg, P-31, S, Cl,, K, Ca, V, Zr, Nb-93, Cd,, Sn, Gd, Ta-181, Pb, Bi-209, Th-232, U-235, U-238, Al-27, F-19, Ar, Ga, Pt, Fe, Cr, Ni, Cu. (Materials appearing twice are taken from different evaluations - ENDF/B-V and ENDF/B-VI - or processed by different computer codes - NJOY and MINX).
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4. METHODS

To produce the Master Library in AMPX format, the NJOY, SMILER, and SCALE sequence of codes have been used.  NJOY-94 has been used to process the ENDF/B-VI basic nuclear data into averaged cross sections and particle transport matrices.
  
The RECONR, BROADR, UNRESR, HEATR, THERMR, GROUPR modules have been used for neutron and gamma-ray production data in GENDF format, while RECONR, GAMINR modules were used for photon interaction.
  
- RECONR: reconstructs pointwise cross sections from resonance parameters;
- BROADR: Doppler broaden and thin pointwise cross sections;
- UNRESR: computes effective pointwise self-shielded cross sections in the unresolved energy range;
- HEATR: produce pointwise kerma factors and radiation damage cross sections;
- THERMR: generates neutron scattering cross sections in the thermal range;
- GROUPR: produces self-shielded multigroup neutron cross sections and group-to-group scattering matrices, and photon production matrices in GENDF format;
- GAMINR: computes multigroup photon interaction cross sections and scattering matrices in GENDF format.
  
The SMILER code, a module of the AMPX-77 code system, has been used to convert multigroup data from the GENDF format into the AMPX format. It merges the neutron and the photon data (from GROUPR and GAMINR, respectively) to provide, nuclide by nuclide, a coupled n-photon library, as final product.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME:  Machine dependent.
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7. UNUSUAL FEATURES

The material characterized by MAT=900 has been added in the library. It contains the ANSI standard neutron/gamma flux to dose rate factors, in the 174n and 38 gamma group structure, to be used for dose rate calculations.
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8. RELATED OR AUXILIARY PROGRAMS:   NJOY, AMPX, SCALE, SCAMPI, DORT, TORT.
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9. STATUS
Package ID Status date Status
NEA-1702/01 25-MAY-2004 Tested at NEADB
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10. 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", ORNL/RSIC-XX, DLC-113, November 1987.
  
- M. Frisoni, G.C. Panini
"RFL-2: A library of nuclear response function in Vitamin-J structure", June 1994 EFF meeting, EFF-DOC-281 (93), NEA Data Bank, Paris
  
- D.G.Cepraga, G.Cambi, M.Frisoni, A.Chiasera:
Water cooled and gas cooled  SEAFP fusion plant models comparison based on the outside-cryostat dose rates., Fusion Engineering and Design 69 (2003) 7
NEA-1702/01, included references:
- G.C.Panini, D.G.Cepraga, G.Cambi, M.Vaccari, E.Menapace, M.Frisoni:
Production and application of the Vitamin-EEA data library for radiation
transport evaluation in fusion reactors using SCALE computational system.
Conference Proceedings Vol.59"Nuclear Data for Science and Technology", Trieste
19-24 1997
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11. HARDWARE REQUIREMENTS:  206 MB.
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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13. SOFTWARE REQUIREMENTS
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

G.C.Panini, ENEA, FIS-MET, Bologna Italy
M.Frisoni, Athena S.a.S, Bologna, Italy
D.G.Cepraga, ENEA, FIS-MET, Bologna Italy
G.Cambi, Bologna University, Physics Department, Italy
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16. MATERIAL AVAILABLE
NEA-1702/01
VitENE-E.ale             ALE output
VitENEA-E.dat            ascii library
Trieste_VitENEA-E.pdf    documentation
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17. CATEGORIES
  • Z. Data.

Keywords: coupled neutron gamma cross sections, dose evaluation, library, multidimensional, radiation transport.