Computer Programs
IAEA1364 ZZ-FENDL-2.
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IAEA1364 ZZ-FENDL-2.

ZZ-FENDL-2, Evaluated Nuclear Data Library for Fusion Neutronics Applications

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1. NAME

ZZ-FENDL-2.0 and ZZ-FENDL-2.1.

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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name Package id Status Status date
ZZ-FENDL-2.0 IAEA1364/02 Arrived 22-JAN-2002
ZZ-FENDL-2.1 IAEA1364/03 Arrived 18-MAR-2005

Machines used:

Package ID Orig. computer Test computer
IAEA1364/02 Many Computers
IAEA1364/03 Many Computers
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3. DESCRIPTION

FENDL: Fusion Evaluated Nuclear Data Library


MATERIALS/NUCLIDES: 1H, 2H, 3H, 3He, 4He, 6Li, 7Li, 9Be, 10B, 11B, 12C, 14N, 15N, 16O, 19F, 23Na, natMg, 27Al, 28Si, 29Si, 30Si, 31P, natS, 35Cl, 37Cl, natK, natCa, 46Ti, 47Ti, 48Ti, 49Ti, 50Ti, natV, 50Cr, 52Cr, 53Cr, 54Cr, 55Mn, 54Fe, 56Fe, 57Fe, 58Fe, 59Co, 58Ni, 60Ni, 61Ni, 62Ni, 64Ni, 63Cu, 65Cu, natGa, natZr, 93Nb, 92Mo, 94Mo, 95Mo, 96Mo, 97Mo, 98Mo, 100Mo, natSn, 181Ta, 182W, 183W, 184W, 186W, 197Au, 206Pb, 207Pb, 208Pb, 209Bi, Photo-atomic data

IAEA1364/02
FENDL version 2.0 consists of the following sublibraries:

- ACTIVATION (FENDL/A-2.0)- neutron activation cross sections for 13006 reactions on 739 targets ranging from 1-H up to 248-Cm at incident energies up to 20 MeV. Pointwise and processed data in different formats are included. Plots are available!
  
- DECAY (FENDL/D-2.0) - decay properties (decay type, decay energy, and half life) for 1867 nuclides and isomers. FENDL/D-2.0 sublibrary is complementary to the activation sublibrary. Pointwise and processed data are included.
  
- DOSIMETRY (FENDL/DS-2.0) - neutron cross sections to be used for reactor neutron dosimetry by foil activation, radiation damage cross-sections, and benchmark neutron spectra. This sublibrary is identical to the International Reactor Dosimetry File (IRDF-90). Pointwise and processed data are included.
  
- FUSION (FENDL/C-2.0) - charged-particle cross sections for the following fusion reactions: 1-H-2(d,n)2-He-3, 1-H-2(d,p)1-H-3, 2-He-3(d,p)2-He-4, 1-H-3(t,2n)2-He-4, and 1-H-3(d,n)2-He-4. Pointwise and processed data are included.
  
- TRANSPORT - validated basic nuclear data (neutron-nucleus interaction including photon production, and photon-atom interaction cross sections) for 57 nuclides relevant for fusion. In addition to the pointwise data (FENDL/E-2.0), the sublibrary also contains processed data FENDL/MG-2.0 and FENDL/MC-2.0 to be used in the discrete-ordinates and Monte Carlo transport calculations respectively.
  
- BENCHMARKS - collection of benchmarks for FENDL-2.0 validation.

IAEA1364/03
FENDL-2.1 includes:
- FENDL/E-2.1: Contains selected evaluated nuclear data files in ENDF-6 format. Temperature: 300K.
- FENDL/MC-2.1: Contains pointwise continuous-energy cross section data in ACE format for MCNP calculations; also includes probability tables (PT) in the unresolved resonance range. Temperature: 300K.
- FENDL/MG-2.1: Contains multigroup cross section data in the 175n/42g Vitamin J energy structure for multigroup transport codes in two formats: MATXS format processed with MATXSR NJOY module and GENDF format processed with GROUPR and GAMINR NJOY modules. Temperature: 300K.
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8. RELATED OR AUXILIARY PROGRAMS
IAEA1364/03
The existing FENDL/DS-2.0 sublibrary for dosimetry was not updated; the use of IRDF-2002 is recommended instead.
FENDL/A-2.0 sublibrary for activation and FENDL/D-2.0 decay data sublibrary were not updated - use of EAF-2003 (JEFF-3.0/A) is recommended.
No changes are recommended to the FENDL/C-2.0 charged-particle sublibrary.
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9. STATUS
Package ID Status date Status
IAEA1364/02 22-JAN-2002 Masterfiled Arrived
IAEA1364/03 18-MAR-2005 Masterfiled Arrived
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10. REFERENCES
IAEA1364/02, included references:
- A.B. Pashchenko, H. Wienke, J. Kopecky,J.-Ch. Sublet and R.A. Forrest:
FENDL/A-2.0 Neutron Activation Cross Section Data Library for Fusion
Applications, Released on March 14, 1997,(IAEA-NDS-173  Rev. 1, October 1998)
- A.B. Pashchenko and H. Wienke:
FENDL2/A-MCNP, FENDL2/A-VITJ_E and FENDL2/A-VITJ_FLAT
The processed FENDL-2 neutron activation cross-section data files,
summary documentation (IAEA-NDS-174 March 1997)
- A.B. Pashchenko and H. Wienke:
FENDL/E-2.0 Evaluated nuclear data library of neutron-nucleus interaction cross
sections and photon production cross sections and photon-atom interaction cross
sections for fusion applications
Released on May 15, 1998 (IAEA-NDS-175, Rev. 3, October 1998)
- H. Wienke and M. Herman:
FENDL/MG-2.0 and FENDL/MC-2.0 The processed cross-section libraries for neutron
photon transport calculations
Version 1, March 1997 (IAEA-NDS-176, Rev. 1, 98/10)
- A.B. Pashchenko and H. Wienke:
FENDL/C-2.0 Charged-Particle Reaction Data Library for Fusion Applications
Version 1 of March 1997, (IAEA-NDS-177 March 1997)
- A.B. Pashchenko, H. Wienke:
FENDL/D-2. Decay Data Library for Fusion Applications, Released on March 14,1997
(IAEA-NDS-178 Rev.0, March 1997)
- R. Forrest and A. Trkov:
Maintain FENDL Library for Fusion Applications
FENDL-2 Library for Fusion Applications - Status and Future Developments
Summary Report of an IAEA Consultant's Meeting, IAEA Vienna 10-12 November 2003
INDC(NDS)-451 (November 2003)
IAEA1364/03, included references:
- R. Forrest and A.Trkov:
'Maintain FENDL Library for Fusion Applications'
FENDL-2 Library for Fusion Applications - Status and Future Developments
Summary Report of an IAEA Consultants' Meeting, IAEA Vienna 10-12 November 2003
INDC(NDS)451 (November 2003)
- D. Lopez Aldama and A. Trkov:
FENDL-2.1 Update of an Evaluated Nuclear Data Library for Fusion Applications
INDC(NDS)-467 (December 2004)
- Robin Forrest and Alberto Mengoni:
IAEA Technical Meeting on Nuclear Data Library for Advanced Systems - Fusion
Devices, International Atomic Energy Agency Vienna, Austria 31 October - 2
November 2007 (INDC(NDS)-0525, April 2008)
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

IAEA
Nuclear Data Section
Wagramer Strasse 5
P.O.Box 100
A-1400 Vienna
Austria

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16. MATERIAL AVAILABLE
IAEA1364/02
ACTIVATION  neutron activation cross sections
DECAY  decay properties
DOSIMETRY  N  X-sec to be used for reactor neutron dosimetry by foil activation
FUSION  charged-particle cross sections for several fusion reactions
TRANSPORT Validated basic nuclear data
BENCHMARKS Collection of benchmarks for FENDL-2.0 validation

IAEA1364/03
FENDL/E-2.1: selected evaluated nuclear data files in ENDF-6 format
FENDL/MC-2.1: pointwise continuous-energy cross section data in ACE format for
MCNP calculations
FENDL/MG-2.1: multigroup cross section data in the 175n/42g Vitamin J energy
structure for multigroup transport codes in MATXS and GENDF formats
SIGACE package for Doppler broadening of ACE-formatted file (for generating
ACE-formatted files at temperatures higher than 300K)
NJOY inputs to generate ACE, MATXS and GENDF files
NJOY-99.90 local updates
Auxiliary programs and WINDOWS batch files used to update and verify the
FENDL-2.1 transport sublibraries
INDC(NDS)-451 document
INDC(NDS)-467 document
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17. CATEGORIES
  • Z. Data

Keywords: cross sections, evaluated data, fusion reactions, group constants.